IPP Annual Report 2007 - Max-Planck-Institut für Plasmaphysik ...

Annual Report 2007
Max-Planck-Institut
für Plasmaphysik
EURATOM Association

Simulation of the plasma radiation load onto the plasma vessel of Wendelstein 7-X. The image shows a tangential 3D
view into the plasma vessel across the triangular symmetry plane of the Wendelstein 7-X plasma. The white points represent
the distribution of start points of the photon tracing calculations localized in toroidal direction and around the last
closed magnetic surface. The finite surface elements of the plasma vessel model are colored according to the element
averaged local heat flux.

Annual Report 2007
The Max-Planck-Institut für Plasmaphysik is an
institute of the Max Planck Gesellschaft, part of
the European Fusion Programme (Euratom) and
an associate member of the Helmholtz-
Gemeinschaft Deutscher Forschungszentren.

The year 2007 saw substantial progress in the establishment of the ITER process.
Following the ratification of the ITER Agreement by all the Parties the International
Organisation came officially into being on 24 th October. The first meeting of the ITER
Council took place on 27 th November. A design review by an international panel of fusion
engineers and scientists (see below) resulted in a set of recommendations which are still
under consideration by the ITER Organisation. The preparation of the site in Cadarache
has started with particular care being taken to minimise the environmental impact. The
EU Domestic Agency, “European Joint Undertaking for ITER and the Development of
Fusion Energy”, known as “Fusion for Energy (F4E)”, with its seat in Barcelona, was
established by the Council of the European Union at its meeting in Brussels on on 27 th
March. Didier Gambier, formerly EU Commission, was subsequently appointed its first
Director by the F4E Governing Board and took up his duties on 1 st October.
For Wendelstein 7-X, the large superconducting stellarator under construction at the
Greifswald site of the Max-Planck Institute for Plasma Physics, the past year has been of
particular importance. The assembly of the first magnet modules was re-started following
a long interruption due to systematic defects in certain non-planar coils and after additional
mechanical reinforcement of the support structure. The assembly plan was completely
revised and a new, much more robust concept developed based on a step-wise
approach towards steady-state operation with fusion-relevant plasmas. This plan results
in the completion of the device in mid-2014 with a temporary divertor and first operation
with short pulses at full power about a year after commissioning. This phase is intended
to demonstrate the main physics aim of this fully optimised stellarator, namely, good
confinement of the α-particles combined with the avoidance of intrinsic plasma currents
which change the topology of the magnetic field. The final, water-cooled divertor for
steady-state operation at full power will follow in a later completion phase. The assembly
is now progressing well. The project team has been reinforced, particularly with engineers.
In order to meet the daily requirements of the device construction, the project
structure has been revised and a new organisational form implemented.
At present, the main focus of the ASDEX Upgrade tokamak programme at the Garching
site is to give physics input to critical elements of the ITER design and to prepare for
ITER operation. In 2007 the main hardware enhancement to ASDEX Upgrade was the
completion of the tungsten programme, allowing for the first time the behaviour of tungsten
as a wall material in a divertor tokamak for ITER-relevant plasma scenarios to be
studied. In order to substantiate the results for an all-tungsten wall, start-up and operation
in 2007 were carried out without any boron coating applied. H-mode discharges
with confinement and stability properties sufficient for the standard operating conditions
envisaged for ITER were achieved. The operational space was found to be restricted by
impurity accumulation for both low heating power at the centre and low density/gas puff
levels. Another restriction is on the use of ICRH with tungsten-coated ICRH limiters,
where impurity ions accelerated in the rectified sheath of the active antennae led to
substantial sputtering and hence influx of tungsten. ECRH heating at the centre of the
plasma continues to be very effective in preventing accumulation.
The scientific goal of plasma theory at the Max-Planck Institute for Plasma Physics is the
ab initio understanding of all the relevant phenomena associated with magnetically confined
plasmas. Conclusions and predictions can be verified on existing experiments and
applied to the planning for Wendelstein 7-X, ITER and the projected demonstration
reactor DEMO. A main thrust is the development of rigorous gyrofluid and gyrokinetic
models for the direct simulation of plasma turbulence and of the resulting energy and
particle transport. The analysis of large-scale magnetic perturbations has also recently
become a focus of attention, not only due to the future possibility of active feedback-

control but also because of the novel physics arising from the interaction with fast fusionproduced
α-particles. More empirically based, but motivated by an overwhelming practical
need, are the contributions of the Institute to edge and divertor-plasma modelling.
JET was operational for the first three months of the year. The ITER-relevant experiments
to elucidate the effect of the toroidal field ripple were a highlight. A noticeable difference
in confinement, toroidal rotation, ELM frequency and amplitude between JET and JT-60U
in Japan was found in otherwise identical discharges. In the following months JET operation
was interrupted to install the ITER-like ICRH antenna as well as a new pellet injection
system. Parallel to the shutdown, the JET EP2 project has proceeded well and the
2008 campaigns C20-C25 were prepared. The MPI for Plasma Physics has been
involved in many of these activities. In particular, two scientists from the Institute were
appointed to support the management of the JET Task Forces S1 and E.
A major new part of the contribution of the Institute to ITER during 2007 was participation
in the design review. The design review panel was divided into working groups
which were charged with evaluating and prioritising the list of open issues in the ITER
design and with finding appropriate solutions. The MPI for Plasma Physics also contributes
actively to the physics definition of ITER via the International Tokamak Physics
Activity. The expertise of the Institute is in demand for a wide range of activities in
support of ITER, based not only on the results from ASDEX Upgrade but also on knowhow
in the Technology, Theory, Materials and Stellarator Divisions. This work ranges
from studies of plasma scenarios to work on specific heating and diagnostic systems.
Within the project “Plasma-facing Materials and Components” the areas of plasma-wall
interaction studies, material modification under plasma exposure, development of new
plasma-facing materials and their characterisation have been merged to form a field of
competence at the Institute. The work supports the development of fusion devices at the
Institute and also generates basic expertise with regard to plasma-facing components in
ITER and fusion reactors. The activities are strongly embedded in the materials research
community: The MPI for Plasma Physics coordinates the large EU Integrated Project
“ExtreMat” with 37 partners and heads the European Task Force on Plasma-Wall
Interactions.
Following a year of consolidation the Directorate and the Board of Scientific Directors
are confident that the project Wendelstein 7-X is now back on track and that the new
completion date will be kept. Fortunately, the ASDEX Upgrade Team has overcome the
limitations caused by the severely damaged flywheel generator EZ4. The excellent work
of the staff in all Divisions in 2007 has ensured that the Institute will continue to play a
central role in international fusion research.
On behalf of the Directorate and the Board of Scientific Directors I would like to thank
them all for their invaluable contributions.
Scientific Director Alex Bradshaw

Tokamak Research
ASDEX Upgrade . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .3
JET Cooperation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .25
Stellarator Research
Wendelstein 7-X . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .29
Laboratory Plasma Devices WEGA and VINETA . . . . . . . . . . . . . .61
ITER
ITER Cooperation Project . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .65
Plasma-wall-interactions and Materials
Plasma-facing Materials and Components . . . . . . . . . . . . . . . . . .71
Plasma Theory
Theoretical Plasma Physics . . . . . . . . . . . . . . . . . . . . . . . . . . . . .81
Supercomputing and other Research Fields
Computer Center Garching . . . . . . . . . . . . . . . . . . . . . . . . . . . . .95
Energy and System Studies . . . . . . . . . . . . . . . . . . . . . . . . . . . . .99
Electron Spectroscopy . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .101
Content
University Contributions to IPP Programme
Cooperation with Universities . . . . . . . . . . . . . . . . . . . . . . . . . .105
University of Augsburg
Lehrstuhl für Experimentelle Plasmaphysik . . . . . . . . . . . . . . . .107
University of Bayreuth
Lehrstuhl für Experimentalphysik III . . . . . . . . . . . . . . . . . . . . . .109
Humboldt-University of Berlin
Arbeitsgruppe Plasmaphysik . . . . . . . . . . . . . . . . . . . . . . . . . . .111
Technical University of Munich
Lehrstuhl für Messsystem- und Sensortechnik . . . . . . . . . . . . .113
University of Stuttgart
Institut für Plasmaforschung (IPF) . . . . . . . . . . . . . . . . . . . . . .115
Publications
Publications . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .119
Lectures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .149
Teams . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .175
Appendix
How to reach IPP in Garching . . . . . . . . . . . . . . . . . . . . . . . . . .178
How to reach Greifswald Branch Institute of IPP . . . . . . . . . . . .179
Organisational structure of
Max-Planck-Institut für Plasmaphysik . . . . . . . . . . . . . . . . . . . .180

Tokamak Research

1 Overview
1.1 Scientific Aims and Operation
The tokamak fusion experiment
ASDEX Upgrade (AUG) is a
medium size divertor tokamak
(major radius R=1.65 m, minor
radius a=0.5 m) with an ITERlike
configuration, high shaping
capability (single null and double-null
divertor, elongation up
to 1.8, triangularity δ up to 0.5)
and a versatile heating system. The design combines the successful
divertor concept with the requirements of a fusion
reactor, in particular the need for an elongated plasma shape
and poloidal magnetic field coils outside the toroidal magnetic
field coils. AUG is close to ITER in its magnetic and
divertor geometry and in particular the relative length of
both divertor legs compared to the plasma dimensions. The
installed heating power of up to 28 MW ensures that the
energy flux through the plasma boundary is equivalent to
that in ITER. The scientific programme gives priority to the
preparation of the design (heating, fuelling, first wall materials),
physics basis and discharge scenarios of ITER and the
exploration of regimes beyond the ITER baseline scenario.
The 2007 programme was co-ordinated by four Task Forces
(TF), which consisted of
– Confinement and performance of the ITER base-line
scenario, the ELMy H-mode, and the advanced scenario
of the “improved H-mode” leading to enhanced performance
and longer inductive pulse lengths by non-inductive
current drive,
– H-mode pedestal physics and ELM mitigation and control,
– Magnetohydrodynamic (MHD) stability, active stabilization
of β limiting instabilities as well as avoidance and
mitigation of disruptions,
– Scrape-off layer and divertor physics with the aim of optimizing
power exhaust and particle control (ash removal)
and optimization of first wall material with emphasis on
tungsten.
The similarity of ASDEX Upgrade to ITER makes it particularly
suited to testing control strategies for shape, plasma
performance and MHD modes. The similarity in cross-section
to other divertor tokamaks as e.g. JET is important in determining
size scalings for core and edge physics. Our programme
largely covers the “High Priority Physics Research
Areas” provided by the ITPA Co-ordinating Committee.
Again, several items have been investigated in joint experiments
at all major tokamaks as proposed by the ITPA
Topical Groups. In summary, the AUG programme in close
collaboration within the EU fusion programme is embedded
in a framework of national (see section 8) and international
collaborations (see section 9).
ASDEX Upgrade
Head: Dr. Otto Gruber
The aim of the ASDEX Upgrade programme is
to prepare the physics base of ITER and DEMO.
The full performance H-mode operation with
unboronized, fully tungsten coated walls achieved
in 2007 is a significant step forward. Progress has
been made in the understanding of ICRH produced
impurities, tungsten wall behaviour and fast
ion losses driven by MHD instabilities. Extensions
of ECRF and installation of active in-vessel
coils for ELM and MHD control are under way.
3
The AUG Programme Committee
(PC) established in 2001
enables the Associations to take
responsibility for our near term
programme. This PC defines the
TFs responsible for the different
elements of our programme, and
approves the experimental programme.
Furthermore, the bodies
that work out the programme
proposals are open to external
participants, and remote participation
in the meetings is used. With this structure, we have
achieved a compromise between the international involvement
and the flexibility that has so far been typical for the
AUG programme. For the 2007 experimental campaign, 60 of
the 178 proposals were from outside IPP from 14 EURATOM
Associates, the US and Japan.
The flexible heating systems of AUG consist first of the
neutral beam heating (NBI) with power up to 20 MW. The ion
cyclotron resonance system (ICRF) is capable of routinely
coupling up to 6 MW in ELMing H-mode discharges, but is
restricted with tungsten (W) wall by W sputtering caused by
light impurities accelerated in the RF antenna sheath. The
present electron cyclotron system ECRH-1 was kept available
up to a coupled power of 1.6 MW, and the first new 1 MW
gyrotron working at two frequencies (105 and 140 GHz)
went into operation allowing pure electron heating (ECRH)
and current drive (ECCD). These versatile heating methods
allow the effects of heat, particle and momentum deposition
on energy and particle transport, MHD stability and fast particle
physics to be separated.
Stationary discharges with up to 10 s flat-top allow steady
state investigations not only on the transport and MHD time
scales but also for up to 10 current diffusion times. The fast
integrated control and data acquisition system (CODAC) is
specially adapted to ITER needs with its machine-independent
design, its integrated discharge scenario control and protection
functions and the large number of real-time diagnostics
with integrated data analysis.
The cause of the malfunction leading to serious damage of
the flywheel generator EZ4 (supplies a part of the poloidal
field coils and heating systems) was resolved in 2006. The
repair of the generator runner and flywheel is underway, the
stator must be renewed and completion is scheduled for
October 2008. This accident has given rise to check and to
substantially improve the safety installations of all three
generators. An additional brake for generator EZ2 was constructed
till spring 2007, followed by an upgrade of the EZ3
brake system at the end of 2007 (section 3.1). The operation
of AUG in 2007 with the remaining generators EZ2 (for the
TF coils) and EZ3 (poloidal field coils and heating systems)
was advanced towards acceptable restrictions by optimized

use of generator power consumption applying lower PF coil
voltages reducing inductive loads and new shape and scenario
evolution accounting better for PF coil interactions. Plasma
currents up to 1 MA at limited triangular plasma shapes,
heating powers up to 7.5 MW and flattop times of more than
5 s were achieved.
In spring 2007 the transition of the AUG vessel to fully
tungsten coated plasma facing surfaces (PFCs) was completed
with the 200 μm W-cladding of the lower outer divertor target
tiles. Careful cleaning of all other tiles was performed to remove
old carbon and boron layers. Accordingly the main emphasis
of the 2007 experimental campaign was on the operation in
an all-metal machine. The proposals were prioritized into W
compatibility of ITER scenarios, extension of the working
space with a metal wall and other ITER related physics
investigations. Plasma operation was accomplished from
April to July and September to October. We conducted 54 long
shifts at high availability with a total of 1150 pulses (technical
tests, diagnostic calibrations and plasma discharges).
1.2 ITER relevant results in 2007
In April 2007 the restart of AUG was done without prior
boronization as the first divertor tokamak operating with a
full tungsten wall. The reduced generator capacity caused
limitations of transformer flux swing, plasma current, plasma
shaping and heating power. In spite of these tough boundary
conditions, a “milestone” pulse was already achieved six
weeks after the first plasma attempt with a full performance
H-mode discharge at β N =2, confinement factor H 98 =1 and a
density of 70 % of the Greenwald density as in previous H-mode
discharges with boronization. No boronizations were performed
throughout the whole campaign. The W concentration
remained at an acceptable level by using central ECRF
at higher heating powers enhancing the turbulent impurity
transport. Obviously the divertor W source has only minor
influence on the plasma W content, which is mainly determined
by the local influx from the low field side limiters
and the central column. The carbon content of a few per
mille did not decrease further, but the net C deposition in the
inner divertor was strongly reduced. This is important for
the tritium co-deposition problem in ITER, as is the whole
W programme for DEMO where the erosion of low-Z material
and the destruction of graphite under neutron bombardment
will be unacceptable (section 2).
The use of ICRF heating is restricted with tungsten walls
by W sputtering caused by accelerated light impurities in
the ICRF antenna near-fields. Therefore the beneficial effect
of ICRH for suppression of W accumulation is offset under
un-boronized conditions. Simulations show an important
influence of the antenna geometry and the resulting box
currents on these electric fields, which will be checked in
2008 after the installation of covering metal corner plates
on one of the antennas.
ASDEX Upgrade
4
During the last years on ASDEX Upgrade the physics base
for ITER operation was significantly extended in both the
foreseen standard H-mode scenario as well as the stationary
improved H-mode (ITER Hybrid) scenario. The progress was
slowed down in 2007 in favour of the tungsten experiments.
Concerning anomalous transport, zonal flows, geodesic acoustic
modes and turbulence k-spectra were investigated by
Doppler reflectometry (section 6.1-6.2). New insights were
gained on the interaction of energetic particles (produced by
ICRH) with TAEs and other modes driven by the fast ions
based on new diagnostics (fast ion loss detectors, SXR, fast
ECE, hopping millimetre-wave reflectometer (from IST),
CO 2 laser) and theoretical tools (section 6.3-6.6). The structures
of ELM produced filaments, pellet ELM triggering,
wall heat loads from ELMs and disruptions, fuel retention in
W surrounding, and disruption mitigation by a fast gas puff
valve close to the plasma have been looked at (section 7).
1.3 Technical Enhancements and Programme in 2008
The restart of AUG is planned for February 2008, again
without boronization and with the main emphasis on reactor
relevant scenarios in an all-metal machine. Assessment of
plasma performance, divertor properties, C retention, erosion,
hydrogen and noble gas balance and operation without intrinsic
C radiation are the main themes. Improved H-modes
at low ITER-like collisionality (may need the revival of
boronizations) and at high densities will be possible with the
increased power from EZ3 extending our operational window.
At the start of the new campaign the EZ3 generator current
will be enhanced providing an increase from 144 MVA to
175 MVA. With the EZ4 flywheel back in operation in
October 2008 and with the experience gained last year the
AUG operation will be boosted into shaped plasma operation
with up to 1.6 MA and more than 20 MW heating power
at pulse lengths lasting for 10 s. This is supported by reliable
tokamak operation including NTM stabilization, ELM and
disruption mitigation. For the 2008 AUG campaign 171 experimental
proposals have been submitted by 84 scientists,
with more than 50 % from outside IPP and including 44 ITPA
joint experiments. A prioritized programme was approved by
the AUG PC and will be conducted by new TF leaders including
one from the UKAEA.
In order to achieve AUG´s programmatic goals and to maintain
a leading position parallel to the ITER construction, it is
necessary to continuously upgrade the AUG diagnostic and
technical systems (section 4). The successful H-mode operation
with an all-tungsten wall has set a milestone. The preparations
of the next major hardware extensions are well
underway with support from other EU Associations. Fast ion
loss detectors for the poloidal distribution of fast ions, CTS
(from RisØ) and beam fluctuation measurements (from HAS)
are the next new diagnostics. The tube geometry of the
blower gun extending the pellet ELM-triggering capability

to frequencies of 140 Hz was optimized. Our ECRF system
is presently being upgraded in power (4 MW provided by
4 gyrotrons), pulse length (10 s) and large deposition variability
(tuneable frequency 105-140 GHz, toroidally and real-time
poloidally steerable mirrors). The first 2-frequency gyrotron
has demonstrated reliable long-pulse operation and substantially
contributed to our results. Central heating, suppression
of NTMs and diagnostic support are the main aims.
The installation of a very flexible and powerful system (toroidal
mode number n≤4) of 24 active in-vessel coils will allow
ELM suppression, tearing mode and rotation control (e.g.
locked mode avoidance). The first 16 coils should be installed
in 2009/10. In connection with a conducting shell structure
they will open up the road for resistive wall mode stabilization.
In the mid term range we will focus even more on advanced
tokamak operation. Reliable creation and sustainment of
optimal current and shear profiles requires an additional offaxis
current drive method such as LHCD with about 4 MW
installed power at AUG. First studies compromising accessibility
and current drive efficiency reveal a driven current
of up to 0.4 MA and the possibility of fully non-inductive
CD at I p =1 MA.
2 Operation with complete W covered first wall
2.1 Preparation of an all-W device
The area of W plasma facing components (PFC) has been
continuously increased since 1999. As the last step to a complete
W coverage of the PFCs, the strike point area of the
lower divertor, the horizontal frames of the ICRF antennae
and all protection tiles for diagnostics were exchanged with
Figure 1 a): View into the outer divertor. The strike point tiles are coated
with a 200 μm VPS W layer, the baffle tiles with a 4 μm PVD W layer. The
Langmuir probes are manufactured from bulk W. b): ICRH antenna with
W-coated protection limiter and striped long-term marker probes (Al, Ni,
Mo and W coatings).
ASDEX Upgrade
5
W-coated tiles. At the strike point position of the outer
divertor W VPS (vacuum plasma spray, 200 μm) coatings
were used in order to ensure an erosion lifetime of several
campaigns. The inner strike point area, as well as the tiles installed
in the main chamber, has been W PVD (physical vapour
deposition) coated with a nominal thickness of 4 μm, similar
to other main chamber PFCs coated in earlier campaigns.
Figure 1 shows photos of newly W-coated areas. In the left
upper part the strike point and the baffle of the outer lower
divertor can be seen, which are equipped with flush mounted
Langmuir probes implemented with W bulk material. The
right picture shows an ICRH frame. The new W-coated limiter
tiles (top and bottom of the frame) are clearly distinguishable
by their brighter appearance. The two striped tiles at the left
and the right side of the limiter frame are long-term marker
probes with Al, Ni, Mo and W coatings.
In order to further minimize the carbon content of the surfaces,
as well as to demonstrate operation with bare W surfaces,
the major part of the previously W-coated tiles were
removed and cleaned mechanically as well as in an ultrasonic
bath. The efficiency of the cleaning was investigated with a
scanning electron microscope. The dominant species in the
(un-cleaned) surface layer were boron, carbon and oxygen in
line with earlier Rutherford back-scattering, nuclear reaction
analysis and secondary ion mass spectroscopy analyses. In
contrast, W is clearly dominating the surface composition
on a cleaned W tile with some contribution of C and minor
amounts of B and O in grooves, holes and arc tracks.
2.2 Start-up with un-boronized W-PFCs
Boronizations were regularly performed to access and to
explore a large operational working space. Each boronization
strongly suppresses the contents of medium-Z impurities
and W (1-2 orders of magnitude).
The reduction of W influxes and the temporal evolution of
the boron coverage are especially evident in ICRH dominated
discharges. The effect of boronization at the ICRF limiters is
only very transient and equilibrium is already reached after
20 discharges. Other areas show longer time constants for
recovering the full W influx but, judging from W influx and W
concentration measurements, a global equilibrium is reached
after about 100 discharges, being less than the typical separation
in-between boronizations of about 200 discharges.
The observed time constants for B erosion and W recovery
are also consistent with estimates on B erosion based on
measured deuterium fluxes and B layer thicknesses. However,
in order to verify these estimations and to allow for
undisturbed D retention studies in W it was decided to startup
without boronization.
After pump-down, the machine was baked at 150 °C for 10
days, which is twice the duration of the usual procedure. In
order to further reduce the absorbed water and nitrogen
from the surfaces, several overnight glows in He (partly with

an admixture of 10 % D 2 ) were performed. The start-up
procedure was slower than usual, because of the technical
constraints (due to the missing fly-wheel generator EZ4)
and a less reliable plasma breakdown and current ramp-up
phase compared to boronized conditions. However, after
about 20 plasma discharges the current flat-top could be
reached and it took only about 5 more discharges to obtain
the first H-modes.
He Conc. (Div) (%)
H98
6
4
2
0
1.2
0.8
0.4
0.0
21700 21800
shot
21900
Figure 2: Temporal evolution of the divertor He/D influx ratio (top) and the
ITER H factor H98 (bottom) in I =0.8 MA, P =7.5 MW discharges. The
p NBI
vertical dashed line denotes the discharge from which on He-glow was no
longer performed.
Figure 2 shows the temporal evolution of the divertor He concentration,
and the ITER H factor H98 during I p =0.8 MA,
P NBI =7.5 MW discharges, starting with # 21700 (the re-commissioning
started around # 21600, but mostly technical trials
were performed and only about 100 s of plasma operation
were accomplished in this initial phase). Although the H
concentration was already quite low (~10 %) and the total
radiation was in the range of 50 %, the confinement remained
at H factors between 0.6-0.8. In parallel, an increasing amount
of He was observed in the plasma discharges, obviously
due to the He overnight glows and the inter-shot He glow
discharges (5 min. duration). Since it is known from experiments
and code calculations that He is de-enriched in the
divertor by a factor of 0.25-0.35, the He concentrations in
the main plasma could have reached values up to 20 %,
consistent with exploratory CXRS measurements. The storage
in and the strong release of He from W surfaces was already
ASDEX Upgrade
6
known from the previous campaign and from accompanying
laboratory experiments, but no strong influence on the confinement
was expected. However, after omitting He glow
completely and performing 3 minutes of D 2 glow only after
disruptions, the He concentrations decreased rather quickly
and, concomitantly, the confinement increased (figure 2,
bottom). Edge density and temperature measurements suggested
that a weak edge transport barrier was at least partly
responsible for the lower confinement with high He content.
Additionally, after the initial conditioning phase it was
found, that inter-shot glow discharges are much less important
for plasma ramp-up and density control, than they have
been with graphite PFCs.
Astonishingly, similar levels of oxygen as in previous campaigns
have been achieved after the initial conditioning
phase with the full W wall without boronization. Post
mortem analysis of the PFCs revealed very low C deposition
at remote areas in the divertor (see MF section), which
reflects the strongly reduced primary C sources. However,
neither C influx measurements at the central column nor
CXR spectroscopy show this strong reduction yet. Typical
values are several 10 20 /s for the gross C-influx and 0.3 % for
the edge C concentration. The reason for the persisting (low)
C influx and content is not yet completely understood, but in
principle it can be explained by the remaining small C
sources and the observed strong C recycling. Therefore, all
PFC has been thoroughly cleaned to start the 2008 campaign
with pure W surfaces.
2.3 Tungsten Influxes
Special emphasis is given to the determination of the tungsten
influx in order to elucidate the details of the erosion processes
and to assign them to specific plasma scenarios. Figure 3
shows the temporal evolution of the W influx at the low
field side limiters, the central column and in the divertor in
an I p =0.8 MA, n e ~7.5⋅10 19 /m³ discharge with continuous
NBI and ECRH as well as alternately switched ICRH.
Simultaneously, the outer radius of the plasma was varied.
The W fluxes from the divertor and the central column (HS)
presented in the bottom part of the figure were calculated
assuming toroidal symmetries. The W influx at the low field
side (LFS) ICRH limiter (W L34 ) increases immediately by
almost one order of magnitude as soon as the corresponding
antenna is powered and it increases generally for larger plasma
radii leading to a smaller gap between separatrix and LFS
limiters. From the temporal behaviour of c W it can be concluded
that the divertor W source, although it is the largest
one compared to the sources from the other areas has only a
minor impact on the W contamination in the plasma. This is
in line with earlier investigations comparing discharges with
the upper W divertor with ones using the lower graphite
divertor and dedicated experiments with W injections at the
mid-plane and in the divertor.

P heat/rad (MW)
W mhd (MJ)
Γ (W-atoms/s)
6 PNI
4
2
0.6
0.4
0.2
c w 10
-4
10 -5
10 -6
10 19
10 18
Prad
PICRH34
Wmhd
WODIV
WL34
PECRH
PICRH12
WHS
# 22247
Rout (req.)
Rout (meas.)
2.0 2.5 3.0 4.0 4.5 5.0
Time (s)
The W influx from the divertor is monitored with high spatial
and temporal resolution allowing ELM resolved measurements.
For high density, low temperature divertor conditions most
of the W erosion fluency (>70 %) is observed during the
ELMs, whereas this fraction drops to about 50 % at higher
divertor temperatures. The deduced sputtering yields show,
that similar to the main chamber the W erosion is dominated
strongly by low-Z impurities.
ASDEX Upgrade
2.18
2.16
2.14
Figure 3: Temporal evolution of edge W concentration (c ) and W influxes
W
(Γ) in a discharge with steady state NBI and ECRH and pulsed operation of
the ICRF antenna pairs 1,2 (P ) and 3,4 (P ) and a scan of the
ICRH12 ICRH34
outer plasma radius (R ) out
W conc. @ 1 keV
10 -3
10 -4
10 -5
med. gas, low ECRH
high gas
low gas
medium gas
10
2.0 2.2 2.4 2.6
time / s
-6
rad. peak. / rel. u.
20
10
med. gas, low ECRH
low gas
medium gas
high gas
0.5
0
2.0 2.2 2.4
0
2.6
time / s
Figure 4: Evolution of tungsten (edge) concentrations, radiation peaking
and stored energy (Wmhd) for discharges with different gas puff levels or
different central ECRH
1
R out (m)
Wmhd / MJ
7
2.4 H-mode operation space
The complete coverage of the first wall with tungsten
caused a reduction of the H-mode operation space in terms
of minimum required values of gas puffing and central heating.
To avoid central tungsten accumulation, higher central
ECRH power was required to allow for a reduction of the
gas puff during H-modes. Figure 4 shows time traces of four
1 MA discharges with different levels of gas puffing and
central ECRH (H98=1 at t=2 s). The cases with reduced
ECRH power or too low gas puff exhibit central radiation
peaking, followed by central tungsten accumulation and a
loss of good H-mode confinement. The accumulation of
tungsten is supposed to be a complicated interplay of neoclassical
inward drift, density peaking and central radiation
losses. Probably due to the reduced heat flux causing reduced
anomalous transport, the increase of central radiation due to
tungsten supports electron density profile peaking, as shown
in figure 5. The density profile peaking in turn drives the
neoclassical accumulation of tungsten in the centre.
n e /m -3
1.5·10 20
1.0·10 20
0.5·10 20
low gas
high/med. gas
med. gas, low ECRH
t=2.5 - 2.55 s
0
0 0.2 0.4 0.6 0.8 1
ρ
pol
Figure 5: Density profiles corresponding to the discharges presented in
Figure 4
2.5 Operation of ICRH
In previous campaigns the ICRH was a routine tool to control
the central W accumulation, because of its high flexibility
for operation at different Bt (2.0 T-2.7 T), but operation of
the ICRF antennas in the full tungsten machine appeared to
be difficult without boronization due to W release from the
PFCs. The quite high levels of low-Z impurities can be considered
as most unfavourable conditions for ICRF operation.
The values of the effective sputtering yields during ICRF
heating can be reduced significantly only in the discharges
with high gas puff rates and large clearance between the
plasma and the first wall. These conditions correspond to
low plasma temperature at the edge. By using ICRF heating
only, type III ELMy H-mode is achieved with radiated

power in the range of 80-90 % of ICRF power. Measurements
of W fluxes indicate antenna limiters as dominant
sources of sputtered W during ICRF. This stresses the role of
antenna near-fields in the W sputtering via rectified sheath
potential. Simulations of the near-fields in a vacuum with
fine geometrical details with the HFSS (High Frequency
Structure Simulator) code are in progress. The simulations
show an important role of the parasitic antenna box currents
on the voltages along magnetic field lines. The contribution
to the voltages shows strong dependence on the antenna limiter
geometry which might require optimization. The role of the
box currents is to be checked in experiments in 2008 after the
installation of covering corners on one of the antennas.
3 Technical Systems
In 2007, for the first time, experiments in a tokamak with a
full tungsten first wall were performed.
The experiment was in operation for 59 days (including 7 technical
shot days) performing 1104 shots in total with 476 shots
useful for the physics programme, which focussed on the
investigation of plasma-tungsten interaction without boronization
of the first wall. Vessel conditioning was performed by
extended backing and glow discharge cleaning. There was no
unscheduled opening in 2007. Nitrogen venting necessary to
calibrate the Thomson scattering diagnostic was used for a
minor readjustment of the divertor manipulator. The shutdown
periods in winter 2006/07 and autumn 2007 were used for diagnostic
improvements and upgrades, in particular bolometer,
pressure gauges and the relocation of the killer gas valve.
Inspection of the in-vessel components during the scheduled
opening in autumn 2007 revealed an excellent state of the first
wall components. The strike line targets were undamaged.
Small amounts of damage were observed at the outer corners
of the roof baffle. Significant arc tracks were found at the transition
and retention module of the inner divertor. The carbon
deposition on first wall components was below a monolayer.
In preparation for the 2008 campaign, the first wall was cleaned
with wet wiping cloths to remove carbon and boron layers.
3.1 Flywheel generators and power supplies in 2007
For ASDEX Upgrade, flywheel generator EZ2 (167 MVA,
1450 MJ stored energy) supplies the toroidal field coils,
while generators EZ3 (144 MVA, 500 MJ stored energy) and
EZ4 (220 MVA, 650 MJ stored energy) supply the poloidal
field coils and additional heating systems. Due to an incident
with EZ4, this generator is under repair until the second half
of 2008. A special working group for “the safe operation of the
generators at IPP”, with specialists from energy supply and
tokamak operation, now co-ordinates the upgrades required to
ensure safe operation of EZ2, EZ3, including the infrastructure,
and to oversee the repairs of EZ4. One example is the installation
of additional independent brakes for EZ2 and EZ3.
ASDEX Upgrade
8
With EZ3 alone, a naïve transfer of all PF and additional
heating circuits which previously connected EZ4 to the
existing connections of EZ3 is not viable, as this would limit
operation to 0.5 MA in H-mode. A critical analysis of the
thyristors used for the poloidal field coils, led to a proposal
to significantly reduce the voltage available to ensure the
best possible use of the thyristors within the limits of EZ3.
Previously, the poloidal field coils were optimised individually
for fast response. With the new configuration, an
acceptable (slower) response to the overall PF set was maintained,
which was tested in July 2006, including the protection
of the generator and power supplies. Successful plasma
operation was obtained with these new settings, starting at
the end of April 2007. The plasma control systems were
optimized to include the new time constants of the power
supplies. More importantly, all plasma start-up and rampdown
scenarios were modified and unified, to cope with the
severely reduced voltages available for the PF coils.
Figure 6: An example of the power saving with the new power supply configuration
to EZ3. Figure (a) Power requirements for EZ3 without changes
to the thyristor settings, compared to an actual discharge from 2007.
Figure (b) at the same input power and plasma current.
An example of the power saving with the new power supply
configuration to EZ3 is given in figure 6. Figure 6a shows
the power requirements (filled area in magenta, representing
the sum of EZ3 and EZ4 currents) of a pulse in 2006, prior
to the changes to the thyristor settings (exceeding the limits
for EZ3 alone, already during the pre-charge phase, t10 s can be
achieved. H-modes at 0.8 MA with up to 12 MW additional
heating and H-modes at 1 MA with up to 8.5 MW were possible
in 2007 to investigate the full tungsten wall at ASDEX
Upgrade. Implementation of the physics programme was
however more tedious compared to previous years due to
operation close to the power limits of the EZ3 generator.

3.2 Torus Pumping and Gas Inlet System
To improve the operational reliability, an additional water
cooling pumping system for the torus pumping system was
installed. The type of turbo molecular pump that is currently
in use is no longer supported and so two different types of
pumps were investigated for their suitability as replacements.
Laboratory tests and in-situ operation of both types
during the 2006/07 campaign led to a decision. The contract
for the delivery of 14 pumps (Pfeiffer TPU 2301 PN) was
closed and the first five pumps have already been delivered
and were installed during the shutdown. Due to the modular
design of the control and hardware system it was possible to
replace the pumps and integrate them into the PLC system
without major changes. The gas matrix system for supplying
the discharge gas valves of the Gas Inlet System was commissioned
at the beginning of 2007 and was routinely operated
during the campaign. During glow discharge cleaning GDC
the pressure in the vessel is now feed back controlled. To
reduce the amount of Helium in AUG the gas species usually
used for GDC has been changed from Helium to Deuterium.
Because of the in vessel cryopump with its high pumping
speed for D 2 , the implementation of a new aligned operation
procedure was necessary. For safety reasons this procedure
is automated with a PLC system to ensure that the amount of
Deuterium is always below the allowed threshold.
A new type of electrode for glow discharge, originally
developed for W7-X, was tested in preparation for installation
in AUG. The original anode material was changed from
carbon to tungsten-coated carbon in accordance with the full
tungsten wall. The modified anode was installed in addition
to the existing four anodes. Tests should prove the applicability
of the principle. The new design with a much smaller
footprint compared to the currently used electrodes would
be of great advantage, especially in terms of the planned invessel
coils and conducting wall.
3.3 Data acquisition and computer infrastructure
A high definition video conference system (LifeSize Room
Sony HD together with a KEM 970 based audio system) has
been put into operation in the ASDEX Upgrade control room
to provide the infrastructure for remote experimental participation.
This technology not only enables European and non-
European Associations to fully participate in local experiment
sessions but also allows AUG to participate in other
experiments worldwide. Figure 7 shows an experiment session
between Garching and JT60U in Naka, Japan. It demonstrates
that the feeling between the parties of being present
and involved with each other has definitely improved. In fact
HD video conferencing implements a new quality in working
together over long distances and considerably improves
the co-operative creativity of participating scientists.
For real time data acquisition purposes a new serial I/O card
has been developed which will allow a broad variety of
ASDEX Upgrade
9
external devices to be directly coupled to computer cPCI and
cPCIe busses. This card is part of a hard- and software concept
which has been defined to support RT DAQ and subsequent
RT Analysis and to deliver diagnostic results into the
AUG Control system for advanced plasma control scenarios
like the MHD identification and stabilization initiative.
Figure 7: Video conferencing (AUG/JT60-U) during an experiment session
3.4 Neutral beam heating
During the 2007 campaign neutral beam injection (NBI)
was provided for 503 out of the 563 discharges classified as
“useful”, underlining the NBI’s role as a workhorse among
the heating systems. Operation of the NBI system was mainly
restricted by the power limitations due to the absence of the
EZ4 flywheel generator in this campaign. Of the 20 MW
installed heating power, supplied by two injectors with four
ion sources each, only up to 10 MW were injected. Additionally,
being not fully conditioned, one of the sources of
the first injector was not operable.
Overall, the systems worked reliably with only the loss of
one RF generator in September. A coil had overheated
because a defective component had led to a permanent
power output of the RF system. The secondary damage
caused by the incident included a shortcut in the 110 m long
RF wire between the generator and ion source and a thermal
deformation of the source’s RF transformer. Repairs were
begun immediately and operation of the respective source
was resumed on the 27 th of September. As a consequence for

the future, a new safety interlock was introduced which
switches off the RF system in case of an unrequested power
output. Whenever the limited time between shots allowed,
conditioning of source no. 2 was continued. This source had
been installed close to the end of the previous campaign as a
replacement for a source which had suffered a water leak.
At the beginning of the 2007 campaign, the source’s extraction
grid system was in a completely unconditioned state.
After about 1300 conditioning shots at the end of the campaign
the source could be operated more or less reliably at
40 kV, where 60 kV is the standard operation voltage of this
injector. Conditioning is expected to be finished during the
2008 campaign.
In the following two months shutdown phase maintenance
of both injectors could be finished in due time for the start of
the next campaign despite an extensive list of tasks. Among
them, all eight titanium evaporator pumps were overhauled.
Traces of melting were discovered on bellows of the cooling
connections to the ion dumps of the second injector. The
bellows were replaced and protection shields installed.
3.5 Ion Cyclotron heating
The ICRF system was ready when ASDEX Upgrade restarted
operation. Now all antennas are equipped with W-coated
limiters. One antenna has an optically closed Faraday
screen, to investigate the influence of shielding the antenna
from plasma, possibly expelled by ELMs into the antenna,
on its voltage standoff capability. One antenna has also been
fitted with the option to locally inject gas and with diagnostics
to measure currents drawn by some limiters. Whereas
experimentation with ICRF has become more difficult, a way
was found to still use ICRF efficiently to heat high density
discharges centrally: a large plasma-antenna distance is beneficial,
together with a high gas puff rate. In terms of plasma
and impurity behaviour, there is no difference between
standard gas puff and local gas puff near the antenna. The
latter however has the advantage that it increases the antenna
coupling resistance, which is low at a large antennaplasma
distance.
One of the power tetrodes failed during operation, increasing
the need to find a solution for the unavailability of replacement
tetrodes. While this tetrode is being refurbished, the
ICRF systems have to operate without any spare tetrode.
The failure of another tetrode would result in a reduction of
the available power by half. The option to modify the generators
to be able to use commercially available tetrodes is
being investigated.
During the AUG vessel opening at the end of the year, diagonal
plates covering the uncompensated top and bottom
parts of the antenna straps have been installed. Calculations
show that the dominant contributions to the electric fields are
due to currents in the antenna box. Consequently, this installation
should not lead to a substantial change in impurity
ASDEX Upgrade
10
production, as long as the fields due to the antenna box
remain the major contribution. Our modelling also shows
that those dominant fields can be reduced, by placing the
antenna in a wall and by having 4 straps with the proper
phasing, rather than 2. A new vacuum chamber, where such
a 4-strap antenna can be tested, was ordered for the new test
facility located in the L7 hall. The contract for the automatic
matching was cancelled as it became clear that the company
that had been working on it since 2000 could not fulfil its
obligations. Alternative options are being investigated. A
complete overhaul of the compressor system providing pressurized
air for the transmission lines is ongoing. It will allow
for faster refilling of those lines and easier maintenance.
3.6 Electron Cyclotron Resonance Heating
In 2007 both ECRH systems were routinely requested for a
large number of ASDEX Upgrade pulses. The main drive
for the use of ECRH was the prevention of central accumulation
of tungsten (see section 2). The old system was back
to full power (i.e. 1.6 MW, 2 s or 0.8 MW, 4 s) after a gyrotron
broken in 2004 was replaced in the last shutdown by a
similar tube, formerly used at W7-AS.
In February 2007 the new 2-frequency gyrotron Odissey-2
was commissioned. The achieved maximum output power
was 910 kW at 140 GHz and 650 kW at 105 GHz, both for
10 s. Using the new gyrotron, the new stainless-steel highpower
long-pulse load from GYCOM has been conditioned
rapidly and has operated very reliably since then. With
140 GHz the gyrotron was used routinely for heating (700 kW,
limited by arcing in torus-side mirror box, for 5 s, limited by
plasma duration). With 105 GHz, first experiments for collective
Thomson Scattering were performed with the new
RisØ-System which receives its signal through the transmission
line of unit 2. The extension of the new ECRH-2 system
with three 4-frequency gyrotrons 105-140 GHz/4×1 MW/10 sec
is ongoing. First short-pulse tests of the modified gyrotron
Odissey-1, which has been equipped with a BN-Brewster
window, were performed at GYCOM up to 1 MW/0.8 MW
at 140 GHz/other frequencies. No arcing on the air-side was
observed, proving the viability of the concept. Actually the
BN-window has been replaced by a diamond window. Final
factory tests are expected soon. For details on the future
planning for the new system see section 4.
4 AUG enhancements
Continuous progress in tokamak research needs hardware
upgrades that enhance the machine’s capabilities into new
directions, according to recent theoretical and experimental
findings. In line with its mission to prepare for ITER,
ASDEX Upgrade is presently being equipped with new
tools that will enable active control of MHD modes both in
the plasma core (sawteeth, NTMs) as well as in the edge

(ELMs, RWMs). In the first area, the upgrade of the ECRH
system from 2 MW to 6 MW at 140 GHz, including multifrequency
capability in the new system, is underway EU
preferential support activity, see also last year’s report). This
system will also allow global profile shaping. Below, we
report on this year’s developments aimed at preparing feedback
controlled deposition using the fast movable mirrors
installed during the upgrade.
In the second area, phase I EU preferential support has been
awarded to stepwise enhance the machine’s capabilities
adding in-vessel coils that can produce helical fields. While
a first step is aimed at ELM control with static perturbation
fields, the later steps include rotating perturbation fields for
interaction with tearing modes and, after the installation of
passive conducting structures close to the plasma, also with RWMs.
The enhancements will become available in a stepwise manner
from 2008 to 2011, allowing new experimental possibilities
in the following years up to ~2015. In addition to the two
enhancements described here, a continuous refinement of
diagnostics is taking place. Furthermore, a conceptual design
has been started together with CEA to explore possibilities
for LHCD on ASDEX Upgrade, which would allow substantial
current profile control together with testing of technological
concepts such as a PAM launcher under ITER relevant
edge conditions.
4.1 ECRH extension and real time MHD control
The ECRH system on ASDEX Upgrade is being extended by
four 1 MW, 10 s multi-frequency units (see section 3.6) in
cooperation with IAP Nishny Novgorod, IPF Stuttgart and
FZ Karlsruhe. New launchers allow fast poloidal steering
during discharges to vary the location of heating and current
drive. One of the main goals of the new system is real-time
control of MHD modes. For this purpose real-time control
of the mirror drivers has to be developed which will allow
the power to be deposited on the respective resonant flux
surfaces, mainly for (2,1)-, (3,2)-NTMs and sawteeth. For
this purpose, new data-acquisition systems for several diagnostics
have been set up and a new structure for real-time
data processing is being developed according to the foreseen
control scheme.
The presence and type of mode is determined by fast magnetic
signal analysis.
The relevant magnetic flux surface is found either by using
fast ECE data or real-time equilibrium reconstruction. Both
tracks are followed: a real-time-capable 60-channel 2-MHz
ECE data acquisition system has been set up. Real-time correlation
analysis of channels including the mode signal from the
fast magnetics is planned. Real-time magnetic diagnostics,
acquiring 75 channels of magnetic probe, flux loop and coil
current data at 10 kHz are in operation. Reconstruction of the
magnetic geometry using function parameterization (FPP)
with a cycle time of 1.1 ms for 20 principal components has
ASDEX Upgrade
11
been achieved. The next step is to include local current profile
information, derived from the MSE diagnostic, recently
upgraded for real-time performance. The output of the ECEand
the FPP analysis will be combined using a Bayesian filter
to get the best guess for the mode location, developed in collaboration
with IPF/Politecnico Milano. In order to deposit
the power onto the identified flux surface, an algorithm is
under development using look-up-tables based on off-line
ECRH beam tracing. The ECRH deposition position can be
controlled independently by modulating the ECRH and
detecting the correlated temperature modulation using ECE
(see figure 8). It is planned to test all components in an open
loop in 2008 and to achieve feedback control in 2009 in line
with the completion of the ECRH system: the second gyrotron
unit is expected to operate in the first half of 2008;
units 3 and 4 will follow in autumn 2008 and spring 2009.
Figure 8: MHD real time control scheme using ECRH
4.2 MHD control with Active Coils and Conducting Wall
The extension of ASDEX Upgrade with in-vessel coils and
conducting wall is being made in several stages, first with
16 coils (stage 1), 8 additional fast midplane coils (stage 2),
12 AC amplifiers (stage 3), conducting wall elements and
active feedback control for resistive wall mode (RWM) stabilization
(stage 4) and, optionally, 12 additional AC amplifiers
for fully individual coil supplies. This extension is
being carried out in collaboration with RFX Padova, KTH
Stockholm and FZ Jülich.
Stationary n=3 and n=2 fields have been found to mitigate/suppress
ELM instabilities. However, the physics of the
effect is unknown to date. The planned coil set is thus designed
for a highly flexible field configuration, e.g. to test
the importance of a resonance between the error field and
rational surfaces in the pedestal region. The toroidal mode
number can be chosen up to n=4, reducing significantly the
parasitic core island size and risk of NTM seeding compared
to n=3. The vacuum field line excursion is reduced from up
to 7 mm for n=3 to 2 mm for n=4 perturbations while maintaining
the same level of ergodisation (Chirikov parameter
σ=3) in the pedestal region (figure 9).

Field line excursion [cm]
1
0.75
0.5
0.25
0
0.2
n=3
n=4
|q|=3/2
0.3
|q|=5/3
0.4
|q|=2
In stages 1 and 2, n=2 and n=4 configurations (each with
four different parity options) are used with a single DC power
supply. In stage 3, 12 AC power amplifiers allow rotating
fields and continuous variation of the poloidal phase. Fast
rotating fields can prevent NTMs from locking to the vessel
wall to delay or avoid disruptions. It is also possible to study
the interaction of modes with the rotating error field, for
example to synchronise the island position with ECCD stabilization
in the O-point. The conducting wall elements in
stage 4 will permit eddy currents to slow down the RWM
growth rate sufficiently for active control. The design work
is supported by 3D stability calculations using the STAR-
WALL code.
The technical design of stage 1 components has been completed.
The upper and lower coils (“B”-coils, see figure 9)
are mounted on the PSL. The winding is embedded in an
epoxy resin and enclosed in a welded thin metal casing for
complete isolation from the plasma. Joule heating by eddy
currents in the casing limits the pulse duration to ~500 Hz at
10 seconds and full rated coil current. For minimum interruption
of ASDEX Upgrade operation, it is planned to install
the B-coils in two successive maintenance periods, in
2009 and 2010. Plasma compatibility tests for an insulating
coil casing for the fast midplane coils are ongoing.
5 Integrated data analysis
|q|=9/4
|q|=2
|q|=7/3
|q|=8/3
|q|=3
|q|=11/4
|q|=5/2
|q|=4
|q|=4
0.5 0.6 0.7 0.8 0.9
normalised poloidal flux
Figure 9: Saddle coils (insert) and field line excursion for n=3 and n=4
The concept of probabilistic data evaluation relies on both a
forward model linking the physical quantities of interest to
the measured data and a statistical model for the measurement
uncertainties and systematic and statistical uncertainties
of model and calibration parameters. The statistical
model provides a measure to prevent over-interpretation by
distinguishing data structures which are due to significant
physical information from structures which are due to statistical
fluctuations (noise) or systematic effects. Physical
ASDEX Upgrade
1.0
12
conditions and prior knowledge about parameters can be
easily applied within a probabilistic approach. The probabilistic
method allows data from single diagnostics to be
consistently and most reliably analysed. Additionally, it is
useful for validation and combination of sets of diagnostics
in a transparent and standardized way. The Integrated Data
Analysis (IDA) approach provides a full probabilistic
model including physical and statistical models of an integrated
set of different diagnostics. The goal of IDA is to
combine data from heterogeneous and complementary
diagnostics to consider all dependencies within and between
diagnostics for obtaining validated and most reliable
results. IDA was applied to i) the determination of the radial
electric field from passive He II emission and ii) the reconstruction
of electron density profiles from Lithium beam
emission spectroscopy in the plasma edge region and from a
combined analysis of Lithium beam and DCN interferometry
data for full density profiles.
5.1 Radial electric field from passive He II emission
This newly developed method is based on passive spectroscopy
of the He II (4→3) transition at 468.57 nm. The optical
head used for these measurements is part of the Lithium beam
diagnostic. Its lines of sight are situated nearly poloidally.
Fibre optics guide the collected light to two Czerny Turner
spectrometers equipped with fast frame transfer CCDs, which
record data from 18 lines of sight with a frame rate of 4 ms.
Figure 10: Analysis of the influence of a wavelength shift on the determined
electric field
In the forward model the spectrally resolved emitted light
along these lines of sight is calculated, taking into account
the relevant atomic processes as well as the various forces
acting on the emitting particles which lead to the diamagnetic
drift and the E×B drift. The projection of the parallel velocity
onto the lines of sight is included. The forward model
relies on the measured profiles of electron density, electron
temperature and the photoemission coefficients which were
determined using the ADAS package. The profiles of He +

density and He + temperature as well as the unknown E r profile
are described with spline parameterizations. The spline
knots are varied until a best fit of the modelled profiles with
the measured profiles within their uncertainties is achieved.
A careful analysis of the influence of all the different input
parameters has been carried out.
Figure 10 shows the reconstruction of E r for different wavelength
calibrations of a weak H-mode just after the L/H transition
(#21181, t=5 s). While the gradient of the E r profile in
the pedestal region as well as the position of the minimum is
unaffected, the magnitude of the E r dip varies strongly with
the wavelength shift.
5.2 Integrated Lithium beam and interferometry data analysis
Electron density profile determination from the lithium
beam (LIB) diagnostic is based on the observation of Li I
radiation at 670.8 nm from neutral lithium atoms injected
with an energy of 15-80 keV into the plasma. The newly developed
probabilistic data analysis tool for the LIB diagnostic
is based on a probabilistic description of the measured spatial
line emission profiles and a forward model (collisionalradiative)
of the simulation of the data for a given density
profile. Since only forward modelling is involved no direct
inversion of the noisy data is necessary. The probabilistic
method has several advantages compared to the conventional
ill-conditioned inversion technique. It is not necessary to measure
the whole emission profile, to fulfil an inner boundary
condition or to provide additional experimental information,
to pre-smooth or bin the data temporally. The cumbersome
numerical problems with the absolute calibration factor are
resolved. The new technique is numerically stable. Consistent
profile uncertainties are provided reflecting all error
sources encountered.
ρ pol
ρ pol
Figure 11: Comparison of the density profiles (#20160) obtained with the
new analysis tool (blue), the classical IPP algorithm (green) and the edge
Thomson scattering diagnostics (red). Left: series of density profiles (3.7s-3.9s)
Right: profile and estimation uncertainties for a single time frame with a
temporal resolution of 1 ms.
Figure 11 depicts density profiles of an H-mode discharge
with medium electron density. The pedestal is well resolved
ASDEX Upgrade
13
for the edge Thomson system and the new LIB analysis tool
whereas the old tool does not provide values at the pedestal
top. The reliability of the profile for the medium density
regime is large for ρ pol >0.93. The error bars become large
for ρ pol

as r/a≈0.75, depending on the q profile (i.e. collisionless
Landau damping), with a frequency scale G→√2 consistent
with theory. As the GAM disappears in the core it is
replaced by an enhanced level of background E r fluctuations
– i.e. random shearing. Random fluctuations are also notably
higher in elongated diverted plasmas. Radially the GAM
frequency is not a smooth function but displays a series of
plateaus a few cm wide coinciding with peaks in the GAM
amplitude, suggesting several zonal flow layers. At the plateau
edges the GAM spectral peak splits into two frequency
branches (see figure 13).
Frequency (kHz)
GAM intensity (arb)
25
20
15
10
5
0.3
0.2
0.1
#20787 Ohmic
κ=1.12 q 95 =3.5
ρ = 0.78
f D rms
-2 ρ = 0.95
-3
-4
plateau
1kHz 100
-1
ω = 4πcs/R [(1+κ) −ε]
peak
spliting
ω = √2cs/R
ρ = 0.99
peak x100
0
0.7 0.8 0.9
Radius ρpol 1.0 1.1
Figure 13: GAM frequency and amplitude radial profile for circular limiter
shot #20787
6.2 Turbulence k-spectra
Doppler reflectometry is a diagnostic technique that combines
the positive aspects of scattering and reflectometry
techniques. By tilting the antenna, a specific fluctuation
wavenumber is selected according to the Bragg scattering condition,
k~2k 0 sinθ. Hence a radially localized measurement
of the turbulence wavenumber spectrum can be measured by
scanning the tilt angle θ. A significant upgrade to the
Doppler reflectometry system is a new channel, which has
been commissioned recently. It consists of a steerable antenna
and a W-band reflectometer to extend the radial coverage
into the core. The new antenna configuration allows for
dynamic wavenumber selection up to 25 cm -1 . Using the
new system, turbulence wavenumber spectra were measured
at various radial positions for L-mode and H-mode discharges.
The k-spectra follow power laws k -α with a clear
transition of the spectral index α at kρ s ~1-2 (see figure 14),
which is consistent with measurements reported from Tore
ASDEX Upgrade
14
Supra. Furthermore, a change in the k-spectra is found when
applying electron cyclotron heating compared to pure NBI
heating, indicating a possible change in the underlying turbulence
properties. However, the data is still subject to
ongoing analysis, especially concerning the values of the
spectral indexes.
~ 2 2
|n(k)| /n [a.u.]
1.0
0.1
0.01
0.001
k -2.2
k -7.1
0.0001
0.3 1
k ρs
5
Figure 14: k-spectrum of the density fluctuations |n(k)| 2 normalized to the
squared density as a function of kρ (logarithmic scales) for an H-mode dis-
s
charge (NBI only) at a radial position of ρ ≈0.96 pol
6.3 Rotation frequencies of MHD modes
Plasma rotation plays an important role in understanding
and controlling MHD activity in fusion devices. However, it
is still debatable which physics mechanisms determine the
rotation frequency f 0 of MHD modes in the plasma rest
frame. To this purpose, various assumptions for f 0 were tested
for NTM and TAE modes. The assumptions for f 0 take the
form of different combinations of frequencies derived from
toroidal velocity, poloidal velocity, electron diamagnetic
velocity and E×B velocity.
In the calculation of f 0 , the toroidal rotation is measured by
CXRS, the poloidal rotation is assumed to be neoclassical
(and is calculated by the NEOART code), the diamagnetic
velocity is computed from the electron density and temperature
profiles and the E×B velocity is measured by Doppler
reflectometry, assuming that the phase velocity of the turbulence
is small. For TAEs the frequency f 0 was compared
with theoretical predictions. The rest frame frequencies during
an NTM were found to be small and the rotation to be in the
ion diamagnetic direction when considering only toroidal
and poloidal fluid velocities. However, with the inclusion of
the diamagnetic velocity f 0 decreased to about 0 kHz, indicating
that NTMs have no intrinsic rotation. In the case of
TAE modes, comparison with prediction from theory indicates
that the diamagnetic velocity is not negligible and should
be included in the calculation of the rotation frequency f 0 .

6.4 TAE structure through high resolution SXR
The internal structure of Toroidal Alfvén Eigenmodes was
studied through a new multichord SXR diagnostic with high
resolution. A total of 32 lines of sight span a full poloidal
cross-section, with 2 MHz sampling rate and 0.5 MHz bandwidth.
A detailed knowledge of the TAE internal structure is
crucial to benchmark the existing theories and make reliable
predictions for future experiments. TAEs with toroidal mode
numbers from n=3 to 7 were excited through ICRH. The
SXR measurements show that these modes peak at midradius
and have displacement values in the range 0.1-1 mm, as
can be seen in figure 15 for the n=4 TAE. A good agreement
with predictions of two linear stability codes, the resistive
MHD code CASTOR and the gyrokinetic code LIGKA, is
found, as shown in figure 15. In particular, the radial position
and width of the TAE dominant peak are well reproduced.
A test of the diagnostic sensitivity to changes in the
shape of the TAE eigenfunction was made by simulating the
SXR measurements with the MHD-Interpretation Code in
the real geometry.
Figure 15: (a) Radial eigenfunction of the n=4 TAE in discharge #21067 from
SXR measurements and (b) as predicted by CASTOR and LIGKA simulations
6.5 Fluctuation coherence analysis
The dual-channel fast frequency hopping millimetre-wave
reflectometer is capable of measuring density fluctuations
from the plasma edge to core, allowing the radial eigenfunction
of n=4 TAE to be obtained using phase perturbation and
coherence data analysis techniques. The phase perturbation
analysis indicates the δn e /n e amplitude whereas the
coherence technique gives the relative strength between different
peaks as well as the sign of the radial eigenfunction as
shown in figure 16. The two techniques reveal similar results,
and in particular the radial structure of n=4 TAE is found
to be in good agreement with numerical predictions from
linear gyrokinetic (LIGKA) and resistive MHD (CASTOR)
ASDEX Upgrade
15
simulations. Modes with upward frequency sweeping at
ρ pol ≈0.2-0.4 (+/-0.05) are observed in the early phase of
some discharges with ICRH power ramp-up and are identified
as possible Alfvén Cascades.
Coherence γ
Cross phase θ 0 (rad)
1
0.9
0.8
0.7
0.6
0.5
0.4
0.3
0.2
0.1
0
3
2
1
0
-1
-2
a)
b)
n=5
n=4
-3
0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1
Normalized radius ρpol Figure 16: Coherence analysis: (a) Coherence profile for n=4 and n=5
TAE modes, (b) Cross-phase profile for n=4 TAE mode for shot #21007
6.6 Collective Thomson Scattering
The collective Thomson scattering (CTS) diagnostic uses
mm-waves generated by the newly installed 1 MW dual
frequency gyrotron as probing radiation at 105 GHz.
Figure 17: First back scattered radiation results
1.1

It measures back-scattered radiation using the other ECRH
antenna and transmission line located in the same port. This
information will be used to infer the 1-D velocity distribution
of the confined fast ions.
The figure 17 above shows the first scattered radiation results,
an important milestone for the diagnostic. The centre most
channels are plotted as a function of time during a plasma
discharge where the receiver antenna is swept twice across
the gyrotron beam. The vertical lines are the time points
where the receiver antenna position is expected to have
maximum overlap. The commissioning is in its final stages
and physics exploitation is expected in the 2008 campaign.
6.7 Radial acceleration of solid hydrogen pellets
Fuelling pellets, injected into the plasma from the magnetic
high field side (HFS), undergo a strong radial acceleration
towards the magnetic low field side (LFS), as observed by a
fast framing camera system. The camera images allow for the
study of the pellet velocity through the whole pellet trajectory
inside the separatrix, revealing a monotonic increase of the
acceleration as the pellet penetrates deeper into the plasma.
The cause of this radial acceleration is thought to originate
from a rocket-effect by the asymmetric ablation of the pellet
surface. The ablation asymmetry is the result of the grad B
drift of the pellet cloud, which is then shifted relative to the
pellet. As the pellet cloud provides shelter for the pellet from
hot plasma electrons, the shift of the cloud towards the LFS
will result in a higher heat flux (i.e. a higher ablation rate) at
the HFS of the pellet, thus there will be a net reaction force on
the pellet caused by the impulse of the leaving particles.
Simulations, based on the simple but yet most powerful pellet
ablation model, the NGS (Neutral Gas Shielding), were performed
to estimate the ablation asymmetry. It was assumed
that the total ablation rate is given by the NGS model, but a
small fraction (ε) of it is asymmetrically produced on the
pellet’s HFS. The corresponding net radial force on the pellet
and hence acceleration is taken into account in the simulation,
resulting in curved pellet trajectories similar to the measurements.
Simulations were performed with pellet and injection
geometry settings identical to those in the measurements.
The asymmetry parameter (ε) was tuned until the simulated
pellet trajectory fitted the measured one separately for each
pellet event, and the corresponding value of ε was considered
as the output of the simulation. Up to now 16 pellet events have
been studied and asymmetry values fell in the range of 3-9 %.
6.8 New stochastic model for the sawtooth crash
The sawtooth oscillation is one of the fundamental instabilities
observed in tokamaks. Still no definitive explanation for
the crash process exists. Incomplete sawtooth reconnection
is often observed. It is associated with an internal m/n=1/1
kink mode which does not vanish after the crash phase (as
would be the case for complete reconnection).
ASDEX Upgrade
16
It was shown that these sawteeth cannot be fully described
by a pure m/n=1/1 mode and that higher harmonics play an
important role during the sawtooth crash phase. We demonstrated
that stochastization appears due to the excitation of
low-order resonances which are present in the corresponding
q-profiles inside the q=1 surface which reflects the key
role of the central q(0)-value. Depending on this value two
completely different situations are possible for one and the
same mode perturbations: (i) the resonant surfaces are present
in the q-profile leading to stochasticity and sawtooth crash
(q(0)=0.7±0.1); (ii) the resonant surfaces are not present,
which means no stochasticity in the system and no crash
event (q(0)=0.9±0.05). Accordingly the central safety factor
value is always less than unity in the case of a non-complete
sawtooth reconnection. Our investigations show that the stochastic
model agrees well with the experimental observations
and can be proposed as a promising candidate for an
explanation of the sawtooth reconnection.
6.9 Extrapolation of AUG H-mode discharges to ITER
Scaling laws predict ITER’s confinement and fusion performance
in H-mode. Besides the well established IPB98(y,2)
law, others have been proposed with a weaker β dependence,
such as Cordey’s (2005) and the GyroBohm scaling laws
(see figure 18).
Q/(Q+5)
1
0.1
0.05
IPB98(y,2) Cordey05
0.1 1
3.23 -1.23 -3.10
35.5 H β q
98 N 95
ES GB
ITER ITER
ITER
0.1 1 0.1 1
1.82 0.18 -2.20
6.07 H Cor β N q 95
2.22 -0.22 -2.71
22.8 H EGB β N q95
Figure 18: 0D figure of merit of Q/(Q+5) assuming a constant Greenwald
fraction for the different scaling laws, versus Q/(Q+5) predicted with the 1D
ASTRA simulations. IPB98(y,2) (red), Cordey 05 (green), GyroBohm (blue)
Theory based dimensionless models also predict the ITER
performance. However, even those based on the same instabilities
yield different core predictions. Moreover they are
strongly sensitive to the pedestal density and temperatures,
which are predicted with large uncertainties. In this work
we extrapolate AUG discharges to ITER, using the information
contained in the scaling laws with additional input
from present experiments, in particular the profile shapes,
the H factors, the thermal normalised pressure β N,th and q 95 .
A profile database of 92 well diagnosed H-mode discharges
has been selected, including only stationary time intervals.
The scaled profiles have then been used for ASTRA simulations
with ITER geometry, in order to predict the P fus and P rad ,
as well as P aux needed to obtain the target β N,th at the given
H-factor. The effect of varying the tungsten concentrations
is also investigated here. Dimensionless figures of merit are

validated against the present database, showing that the
profile shape does not dramatically affect the performance;
however, care is required in the choice of the correct figure
of merit, which is strictly related to the assumptions made.
7 Edge and Divertor
7.1 Large and Small Scale Fluctuations
Recently, large scale fluctuations of electron density and
temperature were found at the pedestal in-between ELMs.
They were investigated in detail with edge Thomson scattering.
The fluctuation amplitudes were analysed, varying the density,
heating power, magnetic field, plasma current and shape. It
was found that the relative amplitudes of the inter-ELM
fluctuations increase mainly with increasing line density.
When approaching the Greenwald density (n GW ) at the plasma
edge the mean relative amplitude of the electron density
fluctuations is at about 30 %. The small scale fluctuations of
the electrons in the pedestal were investigated indirectly by
measuring the parameter η e =L ne /L Te with L ne and L Te as the
gradient lengths of the 1D profiles of electron density and
temperature. So far, values for η e around 2 have been found.
By analysing a larger number of plasma discharges with different
discharge parameters it was found that η e increases
for larger elongation (κ), which is expected theoretically:
At κ≈1.35 η e is around 1.2 and rises up to η e ≈2 at κ≈1.8.
The variation of η e with other plasma parameters will be further
investigated experimentally and compared to the results
of theoretical simulations of actual plasma discharges.
7.2 Radial velocity of filaments
Filaments are coherent substructures that form e.g. during
an ELM crash and propagate through the scrape-off layer
towards the vacuum chamber walls, leading to a localized
energy deposition. Various models have been proposed for
their radial propagation. The models differ with respect to
the damping mechanisms and lead to opposed predictions
on the scaling of the radial propagation velocity with the filament
size, i.e. whether bigger or smaller filaments move
faster. The radial and poloidal/toroidal motion of filaments
has been studied with a recently installed filament probe.
The analysis reveals that bigger filaments move faster, with
radial velocities being in the range of a few km/s. This clearly
excludes the sheath damping model, but agrees quite well
with the polarization current model. This finding is important,
as bigger filaments carry a higher energy content, and –
if they move faster and thus have less time to lose their energy
by parallel transport – deposit more heat on the plasma facing
components. Toroidal rotation velocities have been found to
be in the range of up to the pedestal rotation velocity, indicating
that the filaments start with a rotation equal to the
plasma edge and then slow down on their way out. Furthermore,
the filaments broaden with time due to diffusion, and
ASDEX Upgrade
17
lose particles parallel to the field lines with a rate similar to
a free flow of particles. An extrapolation shows that they are
formed with densities close to separatrix densities, indicating
their origin close to the separatrix.
7.3 Pellet ELM triggering
In order to get a deeper insight into the process of ELM triggering
by pellets, pellet injection was analysed in Ohmic,
L-mode and type-III ELMy H-mode discharges, as well as
in ELM-free phases, type-I ELMs in radiative edge scenarios
and the quiescent H-mode regime. In hot edge type-I plasmas
both spontaneous and triggered ELMs are found to evolve
fastest. Reducing the power flux crossing the separatrix,
results in a slowing down of spontaneous ELM growth but
keeps fast rising triggered ELMs.
10 -3
10 -4
10
3
-5
ELM growths time (s)
4
Spontaneous
Pellet triggered
Pedestal top η (10 -8 Ωm)
5 6
Figure 19: ELM growth times versus pedestal top resistivity (parallel
Spitzer). The data comprise hot edge type-I, radiative type-I and type-III
ensembles (left to right), all discharges are at I = 1 MA.
P
This strong effect is shown in figure 19, adopting the increasing
pedestal top resistivity as a measure for the edge
cooling caused by the power flux reduction. The pellet imposed
perturbation is obviously always strong enough to trigger an
ELM in case conditions in the edge barrier regions are prone
to instability growth. The magnitude of the perturbation is
even strong enough to push the triggered mode into the
regime of nonlinear explosive growth. As the triggering of
the pellet-induced ELM happens rather independently of the
phase of the natural ELM cycle in which the pellet hits the
plasma, it is improbable that this corresponds exactly to the
instant where the plasma becomes linearly unstable. Rather,
it has to be concluded that the edge plasma must be in a nonlinearly
unstable situation over almost the entire ELMcycle,
and that the finite-amplitude perturbation due to the
pellet suffices to excite further growth.
An interesting observation is that the quiescent H-mode
shows stability against the pellet perturbation, indicating
that in this case some transport enhancement in the pedestal
region (presumably due to the observed edge harmonic
=

oscillations) keeps the profiles in a stable regime. Pellet
injection into ohmic plasmas showed a directly pellet driven
MHD perturbation exceeding by far that one present at the
visible ELM onset thought to be in the order required for
ELM triggering. No correlation was found between the
MHD perturbations with pellet particle ablation or deposition
rate, indicating an already saturated driving mechanism.
Lower local plasma energies result however in a reduction
of the MHD excitation attainable by the pellet perturbation.
The correlation between pellet MHD drive and plasma
parameters are now under investigation.
7.4 Parallel plasma flow and radial E-field in the SOL
The fast reciprocating probe located 30 cm above the torus
midplane was used to investigate the SOL from the limiters
up to the separatrix. It was equipped with swept Langmuir
probes facing in co- and counter-current direction. This
allowed the floating potential (V fl ), the electron density (n e )
and temperature (T e ) and the Mach number (M) of the parallel
plasma flow to be measured all at once. Also the plasma
potential V pl =V fl +3.1T e and the radial electric field E r =-∇ r V pl
could be deduced. In a series of ohmic discharges the density
was varied covering a Greenwald density fraction of
f GW =0.21-0.49 with I p =1 MA and B t =-2 T. The outer divertor
was fully attached at f GW =0.21 and fully detached at
f GW =0.49. On both sides of the probe head the same T e was
found, but compared to values from Thomson scattering
(TS) T e was considerably lower for ΔR=R-R sep 1 cm). When the outer
divertor was (partially) detached M≤0.6 was found at the
separatrix decreasing to M≈0.2 at ΔR≈0.5 cm and rising
again further outward (M≤0.4). Close to the separatrix the
Pfirsch-Schüter and “return flow” can cause the observed
flows but for ΔR>0.5 cm there has to be another contribution
like e.g. a transport related flow. Flow and divertor
detachment are possibly related.
7.5 Impurity flux in SOL
Ion fluxes in the SOL were measured by exposure of collector
probes with the midplane manipulator system and subsequent
quantification of deposited deuterium and impurity
elements by ex-situ ion beam analysis. Discharge-resolved
and even time-resolved measurements within one discharge
can be carried out employing rotating cylindrical samples
inside a shield with a 6 mm wide slit aperture extending
88 mm in a radial direction. Increased impurity fluxes are
observed during the low density current ramp-up phase as well
as in plasma configurations with a small separatrix-sample
distance and increased ion cyclotron resonance heating
ASDEX Upgrade
18
(ICRH) power. The increase of the impurity flux in the first
two cases is attributed to an increased wall flux and correspondingly
higher sputtering flux. In the latter case the interaction
of the ICRH antenna with the plasma is expected to
create a local impurity source increasing with heating power.
In recent experimental campaigns, apart from the dominant
first wall element tungsten, the main impurities were calcium
(from ceramic isolation) and steel constituents (Fe, Ni) from
the vacuum vessel. The derived concentrations of c Fe ≈10 -3
and c W ≈10 -5 at the plasma edge are in good agreement with
spectroscopic measurements. In order to quantify the edge
carbon flux with a full tungsten wall configuration a full
metallic probe head (TZM shield, Al cylinder) has been constructed.
A typical residual carbon deposition rate of a few
10 21 m -2 / discharge was detected and no significant temporal
evolution of the carbon flux throughout the 2007 campaign
could be observed similar to spectroscopic investigations
(see Chapter 2).
7.6 Analysis of divertor profiles
Dedicated discharges with strike point sweeps allowed power
load profiles derived from Langmuir probes to be compared,
assuming P LP =(7 k B T e +E rec )Γ i, and IR thermography.
Figure 20 shows profiles of electron temperature, density
and power fluxes along the outer target for the inter-ELM
phase of a medium and a high density H-mode discharge.
Coherent averaging over about 100 ELM cylces was used to
reduce the statistical uncertainties. While the T e profiles
along the target are flat, the density profiles are peaked close
to the separatrix. For the high density H-mode the profiles
indicate partial detachment around the strike point. The target
profiles (T e , n e , j sat , P IR ) are very similar comparing discharges
with carbon (divertor IIb) and tungsten (divertor
IIc) target plates. The electron power width obtained from
the Langmuir probes using a sheath transmission factor of 8 is
a factor 2 shorter than the one obtained from thermography.
Both widths increase with density, compatible to the trend
seen for the electron temperature decay length as obtained
from Thomson scattering measurements. One exponential
decay length is sufficient to fit the power decay for these
medium/high density conditions. While the power widths
obtained from the probes are a factor 2-3 larger than the
expectation 2/7·λ Te midplane , the thermographic widths are
clearly out of range, suggesting dominant effects of fast ion
impact and/or radiation.
During ELMs, similar power loads are observed at the outer
target from Langmuir probe and thermography analysis for
both divertors IIb and IIc. The large deposited ELM energies
observed with thermography at the inner target have
shifted upward, away from the strike zone from divertor
IIb to IIc. A corresponding redistribution of the target currents
indicates that in fact the impact region of fast ions
has shifted upward.

T e [eV]
2
par. heatflux [W/m ]
30
20
10
21333
21301
-3
n e [m ]
1•10
20
8•10
19
6•10
19
4•10
19
2•10
19
0
0
-0.05 0.00 0.05 0.10 0.15
-0.05 0.00 0.05 0.10 0.15
ds sep (div) [m]
ds sep (div) [m]
10 8
|| power fluxes, mapping to omp
IR
λ= 7.2 mm
10
-5 0 5 10
dR (omp) [mm]
6
10 7
LP
λ= 3.3 mm
10
dR (omp) [mm]
6
10 7
LP
λ= 7 mm
-5 0 5 10
sep
sep
Figure 20: Top: Electron temperature and density profiles along the outer
target for a high density and a medium density H-mode discharge. Bottom:
Parallel heatflux at the outer target mapped to the outer midplane (omp)
from IR thermography (dashed line) and Langmuir probes (solid line) for
the medium density (left) and the high density (right) discharge. The
straight dashed lines indicate the decay length fits. Spatial co-ordinate
dR is the distance to the separatrix in the omp at the vertical position of
sep
the magnetic axis.
7.7 ELM divertor heat loads
A detailed experimental analysis of the temporal evolution
of the power deposition on the inner/outer target plates with
both field directions was performed, focusing on the deposition
time scales of ELMs. It was fitted with an analytical
formula, which describes the arrival of energy at the divertor
target plates due to a Maxwellian distribution of collisionless
particles. The ELM power deposition on the divertor
target plates can be well described with this simple expression.
Although the asymmetry of the deposited energy as
well as the maximum power deposition values P in and P out
strictly change with the field direction, the temporal evolution
does not show any significant differences between
cases with normal and reversed field. The ELM instability
time τ ELM , is found to be

the peak ion flux by more than one order of magnitude. At
high density the outer target peak ion flux is by a factor of
2 to 3 larger than experimentally observed while for low
density the agreement is satisfying with respect to the peak
fluxes. Stimulated by measurements from a recently installed
pressure gauge in the outer divertor tile, the model
of the neutral conductance below the divertor target plates
and dome has been changed. This led to an increased asymmetry
of the ion flux in the simulations, closer to the experimental
observations.
7.9 Gas balance measurements
Tritium retention due to co-deposition with carbon is a safety
issue for ITER. As ASDEX Upgrade is now operating with a
tungsten first wall, long term fuel retention should be significantly
reduced. As a first step, gas balance measurements
with a carbon dominated first wall have been evaluated to
get a reference value. To reach ITER relevant divertor conditions,
a high gas flow rate (3⋅10 22 at D/s) is used in the discharges
under consideration. Here, 10-20 % of the gas input
is retained during the discharge. Most of this inventory is
released by outgassing in between discharges or during glow
discharge cleaning. This value agrees within the measurement
error with the amount of D found in deposition layers
by post mortem analysis. To extrapolate towards longer discharge
durations, the temporal evolution of the gas balance
during a discharge has to be investigated. During the plasma
build up ≈75 % of the puffed gas is retained, whereas for
high density flat top phases wall saturation is reached with
2⋅10 22 retained D-atoms. After the wall is saturated, all
puffed gas is pumped away within the error bar.
Phase N puffed N pumped N plasma Balance
Limiter 15.0 0.9 3.7 30 %
Ramp-up 47.0 5.1 6.9 20 %
Low density 460 290 8.9 65 %
Saturation 610 590 7.6 96 %
Shot 1150 984 86 %
Table 1: Number of puffed (Npuffed ) and pumped (Npumped ) particles, as well as
particles contained in the plasma (N ) for consecutive discharge phases
plasma
of #20447. The balance denotes the fraction of (Npumped +Nplasma )/ Npuffed .
Table 1 summarizes the results for a typical standard H-mode
discharge (#20447). N gives the number of particles (in 10 20
atoms), which are puffed, pumped and which are in the plasma
during the specific discharge phase. The balance denotes
the fraction of (N pumped +N plasma )/ N puffed .
ASDEX Upgrade
20
7.10 Disruptions mitigation with a new fast valve
A new valve for disruptions mitigation was commissioned
in the 2007 campaign. It is designed as an in-vessel valve
and satisfies very demanding functional requirements. It has
a short opening time (of the order of 1 ms), a large orifice
(14 mm of diameter) and negligible leakage (

The results from the two devices show similarities which
support the concept of dimensional similarity. Of special
interest are the plasma dynamics in the vicinity of the separatrix
where an abrupt change of the phase velocity direction
is observed. It switches from the electron-diamagnetic drift
direction in the core to the ion-diamagnetic drift direction in
the SOL. The direction of propagation is consistent with the
E×B-drift direction deduced from floating-potential measurements
(see figure 22). Across the entire radial sweep a
potential-density cross phase close to zero was measured,
which is consistent with drift-wave turbulence.
v θ (km/s)
10
5
0
-5
A
magnetic field
A
A
radial electric
fields
vExB A
A
DSOL LSOL
-10
0 10 20 30 40 50
distance to nominal separatrix (mm)
Figure 22: Measured poloidal phase velocities show a reversal as consistent
with the E×B drift
8.2 Doppler reflectometry simulations
In collaboration with the AUG team, the experimental
Doppler reflectometry investigations on AUG have been
accompanied by fullwave simulations at IPF. The code
“IPF-FD3D” is a finite difference time domain code that
solves Maxwell’s equations and the electron equations of
motion in cold plasma. The two-dimensional version of the
code is used to investigate the scattering efficiency of the
Doppler reflectometer at different angles of incidence in the
presence of plasma density fluctuations. In 2007, the incorporation
of measured discharge parameters and profiles into
the code was accomplished and the main work of simulating
actual measurements taken by the reflectometer was started.
In addition, investigation of the scattering efficiency has
been done in slab geometry with linear density profiles, and
simulations with AUG profiles have been started. For slab
geometry in O-mode, it was found that the scattering efficiency
decreases with increasing angle θ between incident
beam and density gradient. At density fluctuation levels
above 2 %, it was found that the returned power at small θ
was also significantly reduced, due to the appearance of
higher scattering orders. In an effort to concentrate the
European reflectometry code development, the European
Reflectometer Code Consortium (ERCC) was founded
under the aegis of IPP. It comprises members from Germany,
France, Spain, and Portugal. In 2008, this work will be continued,
and the coupling of reflectometry simulation and
plasma turbulence simulation will be started.
A
ASDEX Upgrade
21
9 International & European Cooperations
ASDEX Upgrade (AUG) cooperations are organised under
IEA Implementing Agreements (IA), the International
Tokamak Physics Activity (ITPA), bilateral contracts and by
providing support and an open structure at IPP in particular
for the participation of EURATOM Associations in the AUG
scientific programme. In order to give our guests an even
better opportunity to conduct their scientific programme at
AUG, the weekly operation hours of the device have to be
extended. This idea comes from the Commission Services
and the EFDA leadership. IPP has explored the possibility of
increasing the amount of operational time (6 days of AUG
operation instead of 5 per fortnight or increase the number
of extended shifts which have a 30 % higher pulse rate in
comparison with standard shifts). The implementation of
such a step will require an increase in the number of staff by
10 (8.5 engineers/technician, 1.5 physicist), which will only
be possible with substantial external support from the
Associations/EFDA.
9.1 IEA Implementing Agreement
The current role of the Implementing Agreements (IA) as a
vehicle to enable joint experiments proposed by ITPA is
considered to be very important. AUG contributions to such
joint experiments continued in 2007, but their number decreased
due to the concentration of the 2007 AUG programme
on tungsten related topics. For 2008 however, more than 40
contributions to joint experiments are again foreseen.
In 2007 international discussions on the future of IAs were
started in particular with respect to their interaction with
ITER, but no definite conclusion was reached. The IAs
served as the framework for 13 personnel exchanges between
IPP and labs from the US as well as from Korea. A
summary of the collaboration with GA on plasma edge
physics is given in the following.
The effect of the divertor closure on the core plasma poloidal
fuelling profile was investigated by executing ohmic plasmas
similar in configuration and operating space in the AUG
(closed divertor) and DIII-D (open divertor) tokamaks, and
by scrape-off layer modelling using the SOLPS and
UEDGE codes.
At the lowest density, weak dependence of the divertor plasmas
on the divertor closure was observed experimentally. In
both devices the outer divertor plasma is attached to the target
plate, while the inner divertor plasma is partially detached
at the strike point. SOLPS and UEDGE simulations
were validated against the experimental data and predict significantly
more neutral leakage from the inner divertor plasma
for DIII-D, leading to a broader neutral fuelling profile
above the high-field X-point. For both devices the UEDGE
simulations indicate strong poloidal asymmetry of the ion

flux across the separatrix due to classical ion B×B drifts:
strong influx at the top of the plasma, and outflux above the
X-point. The comparison of the experimental and simulation
data was facilitated via common, MDSplus-based databases
generated under the auspices of the ITPA Divertor and SOL
working group.
9.2 EURATOM Associations
The participation of scientists from EURATOM Associations
continued to stay at a high level as in previous years.
In response to the call for participation in the 2008 AUG
campaign more than 160 experimental proposals have been
submitted by 75 scientists. More than 50 % of them are
non-IPP scientists. Besides several proposals from DIII-D,
the majority of external proposals originate from scientists
of 14 different EU Associations. In total the execution of
more than 1400 discharges has been requested. The international
AUG Programme Committee met in December and
approved a prioritized programme of roughly 800 shots.
Besides IPP ten Associations are represented in this body.
Andrew Kirk a scientist from MAST will take over the
management of the AUG Task Force III “SOL & Divertor
physics and first wall materials”. In the following the most
important contributions from Associations made in 2007
are summarized.
DCU – University College Cork:
Progress made during 2007 in the context of the ongoing
collaboration between IPP and University College Cork is
summarized as follows: A significant effort was expended
on CLISTE reconstructions as part of the recalibration of
the MSE diagnostic in light of systematic corrections to
radial channel locations discovered in early 2007. These
involved analysis of discharges with maximal diagnostic
information on rational surface locations to validate q profiles
obtained with MSE.
CLISTE has been extended to improve the modelling of disrupting
plasmas and now can generate interpretive equilibria
(including halo currents) for plasmas as small as 20 cm in
radius resting on divertor structures. The predictive Garching
Equilibrium Code can now generate ITER equilibria in AUG
shotfile format and construction of a database is underway.
The study of TAE character and stability has been completed
from discharges performed during the 2006 experimental
campaign for cases with ICRH only and combined ICRH
and NBI. Using MSE data, the quality of current profile
reconstructions using TAE mode positions from ICRH-only
discharges and ICRH with beatwaves has been confirmed.
These results will be used to describe in detail the nature and
uses of TAE in ASDEX Upgrade. TAE were also observed
in discharges from the first period of the 2007 campaign, the
first using a full tungsten machine. TAE activity from these
discharges differs significantly from the previous campaign
and analysis of the data is in progress.
ASDEX Upgrade
22
ENEA – Consorzio RFX, Padova:
The ORBIT code has been used to study the fast ion
dynamics in AUG and thus to contribute to the analysis of
the fast ion loss diagnostic measurements (FILD). Several
improvements and corrections have been implemented in
the code in order to perform more realistic simulations to
be compared with experimental data. In particular, the use
of equilibria in straight field lines has been assessed; this has
allowed fast ion physics to be studied in the real D-shaped
geometry of the device instead of a circular approximation
with Boozer co-ordinates. The equilibrium quantities are
computed by the VMEC code and adapted to be accessible
by ORBIT. The main application of the code has been a
study of the fast ion losses induced by Neoclassical Tearing
Modes. The influence of the toroidal magnetic field ripple
has been studied as well. As a further improvement electric
field effects have been implemented to deal with rotating
NTMs. An algorithm to obtain stationary conditions has
been introduced by replacing the lost deuterons with new
ones belonging to the same space and velocity distribution,
which characterizes the ions injected by the NBI system.
Simulations with rotating modes have confirmed most of
the results performed with a stationary mode. It has been
observed that at higher mode rotation frequencies larger
losses occur. This partly agrees with the experimental data,
but further analysis is still needed. In addition, investigations
of the internal structure of TAE modes are reported in
section 6.4.
HAS – KFKI Budapest:
The triggering mechanism of type-III ELMs was investigated
in detail by linking the dynamics of pellet-triggered
ELMs to the pellet trajectory. In order to study the pelletinduced
perturbation which triggers the ELM, magnetic
pick-up coil signals were analysed in ohmic discharges.
Methane doped deuterium pellet experiments were carried
out to study the effect of doping on penetration and pellet
cloud properties. Pellets with methane content between 0.44
and 2.4 % were used.
The effect of pellet injection on target plasma radiation was
investigated by the multi-chord SXR and bolometer systems.
An increase of the total radiation during pellet injection was
observed showing radiation coming from the HFS where the
pellet is ablated. SXR investigations revealed a poloidally
symmetric decrease of the plasma emissivity propagating
inwards during pellet ablation (see section 6.7). Temperature
measurements indicate that the emissivity drop is caused by
the cooling of the plasma.
Further testing was done with a new Lithium ion source
with a surface twice that of the usual one. Although up to
6 mA ion current could be reached the long term reliability
of the source is still not sufficient. The possibility of density
fluctuation measurement using the AUG lithium beam diagnostic
was studied with a single channel observation system.

Although the photon statistical fluctuation level was around
10 %, density fluctuations down to 2 % could be well extracted
using correlation techniques. Installation of a fourchannel
fast detection system is foreseen in 2008.
IST – Centro de Fusão Nuclear:
The swept FMCW profile reflectometer system was not
operated during the 2007 campaign due to waveguide renovation
and installation of ECRH protection shutters. Design
studies for alternate bistatic transmission lines are in progress.
Software development has continued with new algorithms
for the automatic analysis of edge pedestal characteristics,
plus investigations of magnetic ripple effects on
X-mode data inversion to improve the density profile
reconstruction accuracy at the plasma edge and SOL.
Validation studies of the real-time reconstruction procedure
for plasma position monitoring using neural networks were
completed. Using a highly optimized code on a dual core
2 GHz Intel CPU the separatrix position in ELMy H-mode
discharges could be tracked with a

Tokamak Edge and Divertor Physics (E2): K. Behringer,
R. Dux, T. Eich, J. Fink, R. Fischer, J. Gafert, M. Gemisic
Adamov, G. Haas, J. Harhausen, N. Hicks, L. Horton,
A. Kallenbach, B. Kurzan, B. Langer, C. Maggi, P. de Marné,
H. Meister, H. W. Müller, H. D. Murmann, R. Neu, J. Neuhauser,
T. Pütterich, R. Pugno, B. Reiter, V. Rohde, W. Sandmann,
A. Scarabosio, A. Schmid, J. Schirmer, M. Sertoli, K.-H. Steuer,
W. Suttrop, E. Wolfrum, M. Wischmeier, D. Yadikin.
Tokamak Physics Division: C. Angioni, A. Bergmann,
R. Bilato, A. Bottino, M. Brüdgam, A. Chankin, D. P. Coster,
T. Görler, S. Gori, S. Günter, T. Hauff, M. Hölzl, F. Jenko,
O. Kardaun, H.-J. Klingshirn, C. Konz, K. Lackner, P. Lauber,
P. Martin, P. Merkel, F. Merz, G. Pautasso, G. Pereverzev,
E. Poli, M.J. Püschel, T. Ribeiro, W. Schneider, E. Schwarz,
B. Scott, M. Sempf, M. Siccinio, E. Strumberger, C. Tichmann,
C. Wigger, Q. Yu.
Technology Division: S. Assas, W. Becker, V. Bobkov,
F. Braun, R. D’Inca, H. Faugel, P. Franzen, M. Fröschle,
B. Heinemann, D. Holtum, C. Hopf, M. Kick, L. Liu, C. Martens,
J.-M. Noterdaeme, S. Obermayer, A. Onyshchenko, R. Riedl,
J. Schäffler, E. Speth, A. Stäbler, P. Turba, E. Würsching.
Garching Computer Centre: C. Hanke, P. Heimann,
J. Maier, H. Reuter, M. Zilker.
Central Technical Services: F. Ascher, R. Blokker, H. Eixenberger,
T. Franke, I. Goldstein, E. Grois, M. Huart, C. Jacob,
R. Jung, C.-P. Käsemann, M. Kircher, K. Klaster, M. Kluger,
J. Lex, G. Lexa, J. Maier, H. Nguyen, G. Raitmeir, F. Stobbe,
F. Zeus.
Materials Research: M. Balden, H. Bolt, H. Greuner,
W. Jacob, K. Krieger, S. Lindig, H. Maier, M. Mayer,
J. Roth, K. Schmid, W. Schustereder, K. Sugiyama.
IPP Greifswald: M. Laux.
IPF University of Stuttgart: E. Holzhauer, W. Kasparek,
H. Kumric, C. Lechte, P. Manz, B. Nold, B. Plaum, M. Ramisch,
U. Stroth.
Humboldt University, Berlin: C. Biedermann, W. Bohmeyer,
R. Radtke, R. Seidel.
FZ Jülich: A. Kreter, A. Litnovsky, O. Neubauer, B. Unterberg,
R. Wolf.
ÖAW, University of Innsbruck, Austria: P. Balan, C. Ionita,
C. Lupo, F. Mehlmann, R. Schrittwieser.
ERM/KMS, Brussels, Belgium: A. Lyssoivan.
IPP, Praha, Czech: J. Adamek, V. Weinzettl.
RISØ, Roskilde, Denmark: H. Bindslev, F. Meo.
TEKES, HUT, Espoo, Finland: V. Hynönen, T. Kurki-
Suonio, M. Mantsinen.
TEKES, VTT, Espoo, Finland: J. Likonen, E. Vainonen-
Ahlgren.
CEA, Cadarache, France: T. Loarer.
EFDA Close Support Unit, Garching: A. Loarte.
HAS, KFKI, Budapest, Hungary: G. Anda, S. Bató,
E. Belonohy, K. Gál, S. Kálvin, G. Kocsis, T. Szepesi,
S. Zoletnik.
ASDEX Upgrade
24
DCU, University College Cork, Ireland: P. McCarthy,
K. Sassenberg.
ENEA, IFP, CNR, Milano, Italy: S. Cirant.
ENEA, Consorzio RFX, Padua, Italy: E. Gaio, M. Gobbin,
L. Marelli, P. Martin, P. Piovesan, V. Toigo.
Riga University, Riga, Latvia: O. Dumbrajs.
IST Lisbon, Portugal: L. Cupido, L. Fattorini, S. da Graça,
M.-E. Manso, J. Santos, F. Serra, A. Silva, P. Varela.
NILPRP, Bucharest, Romania: C.V. Atanasiu, G. Miron.
CIEMAT, Madrid, Spain: F. Tabares.
VR, Stockholm, Sweden: P. Brunsell.
CRPP, Lausanne, Switzerland: T. Dannert.
UKAEA Culham, Abingdon, United Kingdom: C. Challis,
D. Howell, A. Kirk, H. Meyer.
University of Strathclyde, Glasgow, United Kingdom:
M. G. O’Mullane, H. P. Summers, A. D. Whiteford.
INEEL, Idaho, USA: P. Sharpe.
University of Wisconsin, Madison, USA: C. Forest.
John Hopkins University, Maryland, USA: M. Finkenthal.
PPPL, Princeton, USA: C. H. Skinner.
UCSD, San Diego, USA: G. Antar.

Introduction
The first three months of 2007
were devoted to experiments extending
the 2006 programme and
to new experiments such as those
with increased toroidal field (TF)
ripple. The latter revealed a rather
strong detrimental effect on plasma
confinement and density, especially
at low ν*. These results
suggest that a TF ripple of less
than 0.5 % is required in ITER to achieve Q DT =10. For the rest
of 2007, JET activities were focussed on installation of the
ITER-like antenna as well as the new high frequency pellet
injector. Parallel to these shutdown activities the 2008 Workprogramme
(~170 S/T days) was prepared, whereby a modified
procedure was used. Instead of asking EU Associations
for written proposals, the programme was established by the
JET Task Forces (TF). Since autumn 2007 the JET scientific
management has been supported by P. Lang and Th. Eich,
working as deputy TF leaders for TF S1 and E, respectively.
Contributions to campaigns C18-C19
A major outcome of the hybrid scenario experiments at JET was
the fact that in such discharges the performance (mainly in
confinement, but also in β stability) is very similar to standard
H-mode discharges without q-profile modification. The latter
has been produced by means of LHCD in the preheat phase to
prepare a target q-profile which should be maintained by an
increased bootstrap current fraction (f BS ). In 2007 the analysis
concentrated on the q-profile and its time dependence. It has
been shown that in pulses with very similar performance the
q-profile is also almost identical. A systematic study of the
q-profiles in the hybrid pulses has proven that formation of the
q-profile is not efficient. Immediately after starting NBI heating
(0.5 s) the q-profile has a q=1 surface and is very similar to a
non-modified, standard q-profile. Also in the later phase of the
pulse the maximum f BS determined by TRANSP does not exceed
30 %. This is not sufficient to maintain the initial modification.
One reason for such a low f BS at high β N is the large fast particle
fraction caused by the long slowing down time of NBI ions.
The JET part of the ITPA joint experiment MDC-3, involving
also AUG and DIII-D, for the (2/1)-NTM marginal β pol scaling
was continued. Besides IPP, FZ-J, FOM and UKAEA have
been involved in the preparation, execution and in the data
analysis of the 2007 JET experiments on (2/1) NTM scaling.
Together with the database from 2004/6 an independent scaling
of the marginal β pol for the (2/1)-NTM is now possible.
Ion heat transport is predicted to be driven by ITG turbulence
and should exhibit a threshold and a certain stiffness of radial
profiles. Experiments were carried out to investigate the exis-
JET Cooperation
Head: Dr. Josef Schweinzer
JET started 2007 with three months of operation
with the main aims to extend the 2006 programme
and to conduct a TF ripple experiment.
For the rest of the year JET operation was interrupted
to install the ITER-like ICRH antenna.
Parallel to the shutdown, the JET EP2 project
proceeded well and the preparation of the 2008
campaigns with more than 170 S/T days has
been finished. In many of these activities IPP
has been substantially involved.
25
tence of the expected ITG threshold
and the actual stiffness of
ion heat transport in steady-state
scans of the power deposition
profile. Transport simulations
were performed to prepare the
experiment and to assess the experimental
requirements and possibilities.
Ion temperature modulation
experiments done in 2006
have been analysed with validated
diagnostic data. The results
point to a stiffness factor of ion heat transport in the range of
theoretical predictions. A set of experiments on fast ion redistribution
was carried out, using the new fast ion loss scintillator
probe KA3. Fast ion losses were measured and effectively attributed
to MHD activity, such as sawtooth crashes, TAE and high
frequency fishbones. A few sawtooth events have been analysed
in detail to clarify which particles lead to stabilization and thus
cause a destabilizing effect when they are expelled from the
plasma by other processes. Every sawtooth event at sufficiently
low enough plasma density is accompanied by a clearly observed
spike in the detected particle loss signal, which is more
than a factor of three larger than signals from prompt losses of
ICRH induced fast protons. Regarding the risks of first wall
damage in future tokamaks, these experiments have shown that
fast ions are lost at very high energies, of the order of a few MeV,
and that the losses increase significantly with ICRH power.
Due to the limited power-handling capabilities of the future
ITER-like wall (ILW) an effort aimed at mitigating the target
plate power loading associated with AT plasmas was initiated.
The necessity for such a program was further underlined by the
upgraded heating potential foreseen within EP2 enhancements.
To this end a configuration was first established with
good diagnostic coverage of the edge/divertor plasma, followed
by impurity-seeding experiments with Ne and N 2 . It was
established that good ELM control could be achieved with
neon seeding, while maintaining core plasmas compatible
with AT scenarios. The achieved power unloading at the outer
strike point is judged adequate for the ILW-phase but not sufficient
for the inner divertor. Further configurational/impurityseeding
studies will be pursued in 2008 based upon these results.
Otherwise, excellent edge/divertor datasets were obtained.
These provide the basis for ongoing edge modelling studies.
Spatial and temperature calibration of the Kl3b divertor
periscope infra-red camera was performed including a sophisticated
setup of transformation matrices. Furthermore,
new limits of hardware data acquisition have been exploited.
Full toroidal/poloidal resolution IR divertor profiles have
been produced on a 200 us time scale, which is an improvement
of about a factor 5-10. Software optimization for strike
line splitting in ELM mitigation experiments with an edge
ergodised by external field perturbation was accomplished.

From bolometer (KB5) studies in 2006 it was known that the
characteristic spectra of carbon lines emitted from the divertor
region falls in a range where the detection efficiency of
gold is less than 100 %. The goal was to expand the findings
for carbon to other gases commonly used for impurity seeding
experiments such as N 2 and Ne since it is important that the
bolometer correctly register the level of radiation. Unfortunately,
no quantitatively measured spectra exist from the
divertor/X-point region for JET, nor for other experiments
elsewhere. Thus, it was decided to generate radiation coefficients
for various impurities as a function of T e under the
assumption of coronal equilibrium and fold these into the
detection efficiency curve of gold as a first approximation.
Plasma edge and divertor modelling
Current edge codes form an important bridge between results
on present machines and divertor operation on ITER. In
order to place the ITER predictions on a firmer footing, an
effort has been started to verify existing codes by careful
code-code comparison, and then to validate the codes against
the experiment. Previous results of the EDGE2D-NIMBUS,
B2-EIRENE (SOLPS5) comparison for the D only case were
already reported. During C18-C19, these results were extended
to D+C for SOLPS, and some results for D & D+C
for EDGE2D-NIMBUS and EDGE2D-EIRENE were also
obtained. One of the major results was a renewed look at the
atomic data used. For one particular case, the peak target
electron temperature was found to change by a factor of
nearly 10 depending on the choice of atomic data.
SOLPS simulations of AUG plasmas have been compared
with EDGE2D modelling of JET discharges, regarding the
value of radial electric field (E r ) in the SOL. Realistic EDGE2D
cases were run simulating a real JET discharge as a starting
point, with subsequent wide variation of separatrix density and
input power. The relative roles of the Debye sheath, parallel
electron temperature and pressure gradient terms, and ionelectron
friction in the formation of the upstream (at outer
midplane) E r in the SOL could be identified. The simulations
delivered low E r values which are in contradiction to high E r
values measured on both AUG and JET. A possible reason for
this discrepancy lies in the nature of today’s widely used 2D
codes, which ignore non-local kinetic effects in the parallel
transport of heat-carrying electrons that are only very weakly
collisional in the SOL. Such electrons can raise target T e and
thus directly affect the Debye sheath formation.
Enhancements
IPP’s JET-EP diagnostic projects KB5 bolometer and KA3 fast
ion loss scintillator probe have been closed. Both diagnostics
are delivering high quality data. IPP supports various JET-EP2
projects with different levels of involvement. The ICRF group
has contributed to the development of a sub-harmonic arc
JET Cooperation
26
detection system for the new ITER-like ICRF antenna, and
has regularly attended the project board meetings.
In support of the ILW project IPP leads a diagnostic project
to improve the resolution of the divertor infra red measurement.
The new system will be able to measure the power
deposition on the outboard divertor target during type-I
ELMs and should resolve the ELM filamentary structure. In
2007, the TCDI process was finished. The camera was tested
at IPP and will be installed at JET in February 2008. To support
commissioning and in particular to effect efficient scientific
exploitation, additional personnel were recruited.
Tungsten (W) is foreseen as a plasma-facing material for the
ILW project. The determination of W erosion at the divertor
strike points is a scientific and technical challenge due to the
high net erosion over the entire campaign and the very rough
surfaces. A test marker coating consisting of an 8 μm molybdenum
interlayer and 6 μm W marker coating on a plasmasprayed
200 μm W layer on carbon-fibre composite (CFC) has
been analysed with ion beam analysis methods using 3.5 MeV
incident protons. The results from ion beam analysis were in
good agreement with metallographic cross-sections.
W layers with initial thicknesses of 0.8 μm and 1.6 μm were deposited
at the load-bearing septum replacement plate LBSRP14
and exposed over 2004-2006. A maximum mean W erosion of
about 150 nm was observed. Despite this relatively small mean
value the erosion pattern was strongly inhomogeneous, with
total erosion of the initial W layer on the plasma exposed sides
of microscopic ridges of the rough CFC surface. Due to this
strongly inhomogeneous erosion the thicknesses of protective
coating must be considerably thicker than the mean erosion.
In continuation of IPP’s involvement in the ILW project, a new
EFDA task was launched with the purpose to support the
optimisation of the selected coating deposition processes in
preparation for the series production of all CFC W coatings.
This entailed high heat flux testing of W coatings on CFC in
cooperation with the selected contractors in IPP’s high heat
flux facility GLADIS and was supplemented by metallographic
and electron-microscopic investigations. With Plansee SE
the applicability of vacuum plasma-sprayed W coatings on
full-size divertor tiles and a possible alternative were investigated.
The Romanian Association MEdC was supported in
their effort to set up a series production facility. The task
will be continued in 2008 by providing expertise and quality
assurance tests during the production phase.
Scientific Staff
A. Chankin, D. P. Coster, R. Drube, Th. Eich, C. Fuchs, J. Gafert,
M. Garcia Munoz, H. Greuner, J. Hobirk, Ch. Hopf, L. D. Horton,
Ch. Konz, K. Krieger, P. T. Lang, H. Maier, G. Matern, M. Mayer,
M. Maraschek, K. McCormick, R. Neu, J-M. Noterdaeme,
R. Pugno, M. Reich, F. Ryter, J. Schweinzer, A. C. C. Sips,
J. Svensson, A. Stäbler, G. Tardini, W. Treutterer, W. Zeidner.

Stellarator Research

1 Introduction
In 2007 the organisation of the
project Wendelstein 7-X has
further developed. In order to fit
the organisational structure to
the evolving requirements and
especially to improve the efficiency
of change management,
a new sub-division was set up:
The Design and Configuration
division concentrates all departments
dealing with design and with control of the configuration
and its changes. The Quality Management department
now reports directly to the associate director for coordination
to clearly emphasize its importance for the project.
Design and manufacturing of the different components
of the basic device have considerably progressed, as described
in chapter 2 and 3. This work is still accompanied
by strong efforts of the Engineering subdivision (chapter 4)
and by design work and configuration control (chapter 5).
The assembly of the stellarator device and the development
of the related technologies have progressed well, as
Project
Coordination
H.-S. Bosch
(A. Lorenz)
Project Control
A. Lorenz
Documentation
U. Kamionka
Design and
Configuration
D. Hartmann
(R. Brakel)
Design Office
D. Pilopp
Configuration
Management
R. Brakel
Configuration
Space Control
C. Baylard
Wendelstein 7-X
Heads: Dr. Remmelt Haange, Prof. Thomas Klinger
In 2007, construction of Wendelstein 7-X made
great progress. The problems with the non-planar
coils were overcome and delivery of all
components progressed very well. In the fall of
2007, all coils on the first two half-modules
were threaded onto the plasma vessel half-modules
and were fixed to the half-modules of the
central support ring. Assembly of the support
elements started. Measures were implemented
to guarantee that assembly is finished in 2014.
Quality
Management
J.-H. Feist
Engineering
F. Schauer
(V. Bykov)
Design
Engineering
V. Bykov
Development
and Test
D. Hathiramani
Instrumentation
J.P. Kallmeyer
Assoc. Director
Coordination
H.-S. Bosch
29
described in chapter 6. Diagnostics
developments (chapter 7)
and the set-up of heating systems
(chapter 8) as well as the
development of control systems
have continued.
1.1 Project Coordination/Quality
Management
This subdivision comprises two
departments dealing with coordination
activities for the project
Wendelstein 7-X: (I) Project Control is responsible
for the financial planning of the project and for the control
of the expenditures, time planning of all the activities
in the project as well as of the external contracts. It supports
the component responsible officers in handling their industry
contracts as well as in organisational aspects of
the project and in the reporting to all external supervising
bodies, especially the “Projektrat”, the supervising body of
the financing institutions. The department was concerned
with the development of a new planning tool, based on MS
PROJECT 2007.
Project W7-X
T. Klinger R. Haange
Assembly
L. Wegener
(F. Hurd)
On-Site
Co-ordination
S. Gojdka
Device
Assembly
K.H Oelgemöller
Periphery
R. Krampitz
Assembly
Technology
F. Hurd
Figure 1: Organigramme of the Wendelstein 7-X project as of 31 December, 2007
Magnets and
Cryostat
U. Nielsen
(A. Cardella)
Magnet
Manufacturing
K. Riße
Magnet
Testing
J. Baldzuhn
Cryostat
A. Cardella
Supply Systems
and Divertor
M. Wanner
(Th. Rummel)
Power Supplies
Th. Rummel
In-Vessel
Components
R. Stadler
Cryogenics
M. Nagel
Physics
F. Wagner/ R. Wolf
(V. Erckmann)
Diagnostics
R. König
ECRH
V. Erckmann
ICRH
D. Hartmann
NBI
E. Speth
Device Control
J. Schacht
Computing
G. Kühner
Diagnostic
Software
A. Dinklage

It is designed to integrate time and financial planning into
one software solution with interface to SAP. This allows for
automatic reporting to both the management and the supervising
bodies. The concept for this management tool has
been developed jointly with the IPP administration and an
external consultant. (II) The documentation department is
responsible for an independent check of all technical drawings
and CAD-models and for archiving all documents relevant
to the project. An electronic documentation system
(agile-PLM) is used for archiving documents and CAD
models (in CADDS5-format). Because of the increased use
of CATIA v5 for design and collision investigations, a prototype
interface has been implemented to allow archiving. A
third department, quality management (QM), reports directly
to the project directors via the associate director coordination.
The department organises the QM system within the
project W7-X and supports all external contractors. It took
over responsibilities for quality assurance during the assembly
phase of Wendelstein 7-X. In addition, the QM system, which
was formerly based on the ISO 9001:1994 standards, has
been updated and adjusted according to the ISO 9010:2000
rules. The difference is that the new rules are more concerned
with processes and not anymore with products,
which is much better suited for the a prototype like W7-X.
1.2 Schedule
With the superconducting coils becoming available, the preassembly
of the first two half-modules resumed in spring
2006. The last coils were threaded onto the plasma vessel in
September and thereafter the central support ring and the
support elements were assembled. Pre-assembly of the first
two magnet half-modules is scheduled to be finished by
March 2008. As outlined in the previous annual report, the
project had proposed to set-up a second assembly line for
the magnet half-modules and the magnet modules in order
to accelerate the assembly process. This proposal has not
been approved due to the uncertain delivery situation of the
components. Instead, the project undertook another thorough
review of the assembly sequences: By introducing
additional shift work and some simplification of the
machine for first plasma operation, the machine assembly
will be completed in 2014 without an increase in the project
budget up to end 2014. Starting from the most recent schedule
for the assembly, various changes in the project planning
were investigated in order to make considerable savings in
time whilst remaining within the budget. The remaining
risks both in the schedule and in the budget were minimised,
too. The schedule can be kept only by a staged approach for
the operation of W7-X (“scenario 3”), i.e., instead of equipping
the experiment for steady-state operation immediately,
three consecutive phases are proposed:
1) In the first operations phase without the full set of “invessel”
components the fundamental stellarator proper-
Wendelstein 7-X
30
ties and optimisation procedures are investigated with
plasma discharges of 5-10 s duration. This phase should
last no longer than 2 years.
2) During a subsequent shut down of approximately 1 year
(“completion phase”) construction of the machine for
steady-state operation is completed.
3) The transition to steady-state operation is made in a second
operations phase with a water-cooled divertor and all
other in-vessel components. In this phase the physics and
technology questions in connection with ITER and
DEMO can be addressed.
The following measures are required to ensure the completion
of the assembly by 2014:
– Reduction in the number of ports (by 15 %)
– Installation of a much simpler, inertially cooled divertor
– Shifting some components that are not necessary for the
first operations phase into the completion phase
– Intensifying shift work
– Increasing parallel assembly steps by procuring additional
assembly equipment
Implementation of scenario 3 has started in the fall of 2007.
It foresees the end of assembly and start of commissioning
in May 2014. At the end of 2007, the first two half-modules
have been equipped with seven coils each and these coils
have been fixed to the central support ring. Presently the
inter-coil support elements are assembled.
2 Magnets and Cryostat
2.1 Magnet System
2.1.1 Superconducting Coils
The superconducting coil system of the W7-X consists of
50 non-planar and 20 planar coils. The coils are based on a
special developed cable-in-conduit superconductor that is
composed of an NbTi cable enclosed by an aluminium
jacket. The void within the cable bundle is used for the helium
coolant. The production of the superconductor for the
70 superconducting magnets and the spare lengths has been
completed. The non-planar coils have been contracted to a
consortium formed by Babcock Noell GmbH and ASG
Superconductors S.p.A. 46 non-planar coils have been completed
until end of 2007. 23 of them are accepted for assembly,
two coils are currently tested and 21 coils are pending
for tests in the facilities at CEA Saclay or Forschungszentrum
Karlsruhe (see below). The last 4 coils will be
delivered until March 2008. The aim of non-planar coil production
was to reach series production with a delivery frequency
of two or three coils per month in the year 2007.
Another important goal was to finalise the necessary repair
actions on the coil insulation. Both have been achieved.
The application of an additional HV test under so-called
Paschen-minimum conditions (reduced pressures) turned
out to be very useful to investigate the insulation quality.

The manufacture of the 20 planar coils at Tesla Engineering
Ltd. has been finished in November 2007. 10 coils passed
successfully the acceptance tests under cryogenic conditions.
Wendelstein 7-X
31
2.1.3 Coil Support Structure
The coil support structure is being manufactured by the
Spanish contractor Equipos Nucleares, S.A. (ENSA). It consists
of ten identical sectors with a total weight of 72 t made
from steel plates and cast extensions. The final precision
machining is performed by ENSA subcontractor Rovera
C.M., Italy. The 1 st and 2 nd half-modules of the module 5
have been completed and delivered to IPP at the beginning
of 2007. Both were successfully assembled with the coils
meeting the tight manufacturing tolerances (0.1 mm). The
final machining of the 3 rd and 4 th half-modules (module #1)
has been successfully completed in Rovera in the second
half of 2007. The components were then delivered to ENSA
for the installation of the cooling tubes and the instrumentation.
The components are planned to arrive in IPP at the
beginning 2008. Rovera has already started performing the
final machining of the 5 th and 6 th half-modules and ENSA is
also in parallel completing the main body construction and
extension assembly of the 7 th half-module.
2.1.2 Coil Tests
As in the years before, each superconducting coil for W7-X
is tested in the cryogenic coil test facility of the Commissariat
à l’Énergie Atomique (CEA) in Saclay, France. In
2007 a total number of tests on 13 non-planar and 5 planar
could be finished successfully. Several improvements of the
test procedure were implemented. Additional Paschen tests
and vacuum leak tests, performed on each individual coil at
IPP, complement the CEA tests and complete the acceptance
checks. In the mean time coil testing became routine. Henceforth
no significant quality problems are expected for the
remaining coils. During the whole year 2007, the test facility
worked without major interruptions or technical malfunctions.
It seems that all systematic manufacturing weaknesses
on the coils are now localised, detected and repaired. Hence,
one can be optimistic that coil tests can be financed right in
time for the assembly of the W7-X coil system. In parallel to
the coil tests at CEA, the TOSKA facility of the Forschungszentrum
Karlsruhe (FZK) is refurbished to test coils in 2008
and 2009. For that purpose, a contract was signed between
FZK and IPP to define the mutual tasks during re-activation
of the facility and the test procedure of the coils, and to
commit the contractual payments from IPP to FZK. Several
major tasks were already tackled, both by IPP and FZK,
to prepare TOSKA for re-operation. For instance, FZK
purchased a new vacuum pump system, maintained and
modified the high current power supply, installed the warm
bus-bars, modified the current-leads, made the design for
the current-lead extensions, procured the cryogenic valve
system and the racks for the electronics, finalised the concept
for an entirely new data acquisition system, the safety
and quench detection control electronics, the feed-forward
control electronics for the operation of TOSKA and the helium Figure 2: Installation of the cooling tubes
liquefier and all cryogenics installations, defined all parameters
and interfaces between machine control, data acquisition,
storage and data base system. IPP recruited and
trained the coil test crew, made the design for the cryogenic
high-current joints and manufactured the hardware, built up
the entire cryogenic bus-bar system and all mechanical support
structures inside the TOSKA cryostat, procured and
tested the actively cooled test frames as well as the mechanical
base plate, provided the test electronics for the DC- and
AC-testers as well as the sensor test system, manufactured
the cryogenic cable harnesses, finalised the concept and
design of the coil joints and the removable bus-bar system
directly on the coils, and will provide the hardware for it. It
is envisaged to deliver the first coils to Karlsruhe beginning
of 2008 for testing. Presently a start-up scenario for the
commissioning of the entire test facility is being developed. Figure 3: Front view of module 5.0

Three contracts have been awarded for the R&D and the
manufacturing of the vertical supports of the coil support
structure (“cryolegs”): Zanon s.pa. Italy for the metallic
structure, IMA for the GFC parts, SKF for the sliding and
spherical bearings.
The tests of the sliding and spherical bearings are being
prepared.
2.1.4 Inter-coil Supports
Several support types connect the coils to each other. The
Narrow Support Elements (NSE) between non planar coils
bear pressure loads allowing sliding and tilting. All the
NSE-Pads and -frames of the half-modules 5.0 and 5.1 are
now completed and assembled with the exception of the
NSE elements between the half-modules, which waits for
the completion and assembly of the half-modules into modules.
The Lateral Support Elements (LSE) are welded to the
non planar coils. They rigidly interconnect adjacent coils at
their outer perimeter. The semi products of the LSE for
module 5.0 and 5.1 have been manufactured. The final, custom
machining will be performed after the as-built geometry
between the coils has been measured. The planar support
elements (PSE) connect the planar coils to the non planar
coils. The first PSE (type A1) for HM 5.0 has been success-
Wendelstein 7-X
Figure 4: Test of bearings for cryolegs Figure 5: Detail of the bearing for cryolegs
32
fully completed and installed. The second PSE A1 and the
PSE (type B1) for HM 5.1 are under completion.
Figure 6: PSE A1 installed on the coils
2.2 Vessel and Cryostat
The plasma is surrounded by the plasma vessel, which follows
the plasma contour and constitutes the first ultra-highvacuum
barrier. The entire superconducting coil system is

assembled between the plasma vessel and the outer vessel,
which function as a cryostat keeping the magnet system at
cryogenic temperature and constitute the boundary between
W7-X main device and the external environment.
254 (reduced by 45) ports, manufactured by Romabau
Gerinox, give access to the plasma vessel for diagnostics,
additional heating and supply lines. Deggendorfer Werft und
Eisenbau GmbH (MAN DWE) are responsible for manufacturing
the plasma vessel, the outer vessel and the thermal
insulation.
2.2.1 Plasma Vessel
The plasma vessel consists of ten half-modules, each divided
into two sectors to allow stringing of the innermost
coil during assembly. Construction of the plasma vessel
required 200 steel rings to be bent to the designed shape and
carefully welded to represent the changing cross-section of
the vessel with an accuracy of its final shape 3 to 7 mm.
Vacuum tightness of the welds was checked by an integral
helium leak test of the vessel segments prior to cutting the
holes for the ports. Water pipes around the vessel allow
control of its temperature during plasma operation and for
bake-out at 150 °C. Manufacture of all ten half-modules has
been completed in 2005 and installation of the thermal
insulation has started. The first Rogowski and saddle coils
for magnetic diagnostic have been mounted on the outside
of the first vessel sector during assembly preparation. The
two half-modules (50 and 51) have been integrated with all
coils. The two sectors forming a half-module have been
joined by welding. In both cases the welding was achieved
with very low shrinkage, applying the results of the R&D
performed in 2006 to optimise and qualify the procedure.
The cooling pipe inlet and outlet lines have been manufactured
and assembled. These run between the several components
inside the cryostat and exit from the outer vessel.
Their routing and accurate 3D bending has been more time
consuming than expected but finally arrived in time. The
two main brackets of the plasma vessel are being manufactured.
Their design had to be modified because of collisions
and interface problems with the thermal insulation.
The first two plasma vessel vertical supports have been
completed by MAN DWE. The horizontal support/centring
system design has been completed.
2.2.2 Outer Vessel
The outer vessel consist of five lower and upper half-shells
and will have 524 domes for ports, supply lines, access
ports, instrumentation feed through and magnetic diagnostics.
All upper and lower main bodies of the half-shells of
the outer vessel have been manufactured. Cutting of all
the openings of all the modules has been finished. The details
of the design of the vessel support to the machine bed
have been finalised. The half-modules 5.0, 5.1, 1.0 and 1.1
Wendelstein 7-X
33
have been basically completed in MAN DWE. The first
acceptance tests of half modules 4.0 and 4.1 have being successfully
performed in December 2007. In parallel MAN
DWE is completing the assembly of the domes of halfmodules
2.1 and 2.0.
Figure 7: Pre-assembled lower and upper shells of module 5
2.2.3 Ports
A total of 254 ports are used to evacuate the plasma vessel,
for plasma diagnostics and heating, as well as for supply
lines and sensor cables. The cross sections of the ports
range between 100 mm circular up to 400×1000 mm 2
square and are equipped with bellows to compensate deformations
and displacements of the plasma vessel with
respect to the outer vessel. The ports are surrounded by
water pipes to control their temperature. All ports and their
fixing tools have been delivered in 2007 and the contract
with Romabau has been successfully concluded.
Figure 8: Port

Figure 9: Fixing tool of the port
3 Supply System and Divertor
3.1 Current Leads
Fourteen current leads are able to carry 18 kA each to connect
the seven groups of superconducting coils to the corresponding
power supplies. Forschungszentrum Karlsruhe
(FZK) is developing, designing, manufacturing and testing
the current leads. The current leads contain high temperature
superconducting (HTC-) material in order to keep the refrigeration
requirements small. A particular feature of the
leads is that they are operated upside down, i.e. with the
cold end on top. Therefore the design of the heat exchanger
has to avoid free convection within the flow channels. Free
convection would short-circuit the heat flow between inlet
and outlet and degrade performance particularly at small
flow velocities. FZK has successfully tested a prototype
heat exchanger in upside-down position and verified that
the envisaged HTC-superconducting tapes have the required
critical current of 34 A at a temperature of 77 K and a
magnetic induction of 150 mT. Electrical insulation of the
current-lead housing from the W7-X cryostat requires the
development of a glass fibre reinforced flange. Tests on a
sample flange have demonstrated its capability to take the
specified forces and moments. The interfaces of the helium
cooling lines with the bus lines, the cold electrical contact
and the heat exchanger were defined and fixed. Instrumentation
will be mostly provided by IPP to ensure compatibility
with the cryostat instrumentation. The detailed design
of the current leads was meanwhile completed by FZK. The
mechanical supports of the current leads against the W7-X
cryostat still need to be adapted to keep the loads and
moments during cool-down and magnet operation within
acceptable limits. Design of the test facilities was continued
by FZK. The facilities comprise distribution box, cryogenic
transfer lines and a test box for the current leads.
Wendelstein 7-X
34
IPP supports the design and construction with personnel
resources and will provide cold and warm contacts as well
as a unit of the quench detection system (see below) for the
tests of the leads.
3.2 Magnet Power Supply
The five types of non-planar and two types of planar coils
are energised by power supplies providing direct currents of
up to 20 kA at voltages of up to 30 V. Fast and reliable discharge
of the superconducting magnets in case of quenching
is realised by fast circuit switches which short-circuit the
coils and dump the magnetic energy into nickel resistors The
manufacturer ABB has demonstrated that the current can be
stabilised to an accuracy of 2×10 -3 . Following the delivery
of the final documentation and a training of operators,
acceptance of the power supply and magnet protection
system was declared mid 2007. Since then some practical
experience has been gained with the system. The special
rubber water hoses which isolate the water supply from
high-voltage in case of a rapid shut-down had to be replaced
because their resistivity decreased intolerably with time.
The quench detection system was developed in cooperation
with FZK. The system consists of some 325 quench detection
(QD) units which permanently check the differential
voltages across the double layers of the coils, all sectors of
the bus system and the superconducting part of the current
leads. The system has to reliably detect millivolt signals in a
broadband noise environment and operate at high voltages
during a rapid shutdown of the magnets. The first QD subsystem
consists of 72 quench detection units, a data acquisition
system and an internal battery buffered AC-DC power
converter. It has successfully passed works tests and was
delivered to Greifswald. Safety analyses have shown that
potential grounding faults of a magnet coil should be detectable
during magnet operation. This would reduce the
risk of a high-voltage discharge in case of a rapid shut-down
and simultaneous degradation of the insulation vacuum. In
particular, the application of short high voltage pulses to a
set of ten magnet coils connected in series and simultaneously
measuring the leakage current would detect any
degradation. This option will be further detailed.
3.3 Thermal Insulation
Protection of the cold components against thermal radiation
is achieved by actively cooled shields, high vacuum, and
20 layers of reflecting foils. The fabrication of the panels for
the plasma vessel uses a novel, patented technology to
achieve the required narrow tolerance of ±2 mm. Epoxy
impregnated glass fibre mats are joined with segmented
copper meshes to achieve panels with good lateral heat conductivity
while keeping eddy currents low. All 200 panels
for the whole plasma vessel are available and put on stock.
The holes for the ports and the fixation holes for the

mechanical supports on the plasma vessel are already integrated
according to their actual position in the individual
modules. The panels for the 1 st and 2 nd half-module of the
plasma vessel have been mounted. Also 20 % of the panels
of the 3 rd and 4 th half modules have already been mounted.
Due to the narrow space the panels have to follow the surface
of the plasma vessel at a close distance. Nevertheless
several areas of the panels have to be adapted and cut-outs
have been introduced on a case by case basis to avoid collisions
with neighbouring components. The panels are kept at
temperatures between 50 K and 80 K by cold helium gas.
The panels of the ports and the outer vessel will be made
from brass to limit eddie currents. All multilayer reflective
shields are made from double side aluminised Kapton with a
glass tissue spacer. During integration of the insulation,
great care has to be taken to avoid gaps for heat radiation
between neighbouring panels. The water pipes between the
outer vessel and the plasma vessel also need to be insulated
against the cold parts. Applying the thermal insulation onto
these lines is a particular difficult task since these lines have
a complicated three-dimensional shape and have to pass
through narrow zones between the cold non-planar coils.
3.4 Cryo-Piping
Supply and collection of the cold helium gas of the nonplanar
and planar coil windings, the coil casings, the coil
support structure, the bus lines, the current leads, and the
thermal insulation requires a complex pipe system with a
total length of approx. 3000 m. The main supply from the
magnet distribution box located underneath the cryostat is fed
to eight ring lines inside the cryostat with inner diameters of
16-36 mm. Approximately 460 branch lines with smaller
diameters and lengths between 1 and 11 m connect the different
cryogenic consumers with these ring lines. Routing of
the cryo-lines around the magnet system has to consider
movements of the coil headers during magnet ramping to
avoid collisions with the bus lines and other neighbouring
components and keep sufficient distance to the warmer thermal
insulation. Allowance for the movements is achieved by
flexible hoses. Since the coil casings are supplied in parallel
their pressure drops can be manually adjusted and matched
by 70 cryogenic control valves. A call for tender for the detail
design and construction of the cryo-piping has been launched
and the proposals are being evaluated. Since the cobalt content
of the steel pipes must not exceed 500 ppm the material
for the piping was ordered in advance and will be provided
at the manufacturer’s disposal at the start of manufacture.
3.5 In-Vessel Components
The in-vessel components are the divertor target plates and
baffles for energy and particle control, panels and heat
shields to protect the plasma vessel against plasma radiation,
control coils to modify the magnetic configuration at
Wendelstein 7-X
35
the plasma boundary, cryo-pumps to control the neutral gas
density during high-density plasma operation and supply
lines for heat removal. Plansee SE is manufacturing the
target elements, MAN DWE the wall protection panels and
BNG the control coils. Assembly of the target modules
from target elements as well as fabrication of the baffles, the
heat shields, the cryo-pumps and of the supply lines is performed
by the central technical services of IPP in Garching.
All in-vessel components are fully tested in Garching
(geometry, He-leak tests and hydraulic tests) before delivery
to Greifswald (see figure 10). Several areas with different
heat loads can be distinguished: The horizontal and vertical
target modules of the high heat flux divertor are designed to
withstand power fluxes up to 10 MW/m 2 . The baffles, which
prevent the neutrals from re-entering the main plasma
chamber, receive power fluxes of up to 0.5 MW/m 2 . The
wall is subject to neutral particles and plasma radiation in
the range up to 0.3 MW/m 2 . Following a critical review of
the project scheduled during summer of 2007, it was decided
to start with a test divertor unit (TDU) without water
cooling during the first operation period. The TDU shall be
designed for short pulses at a maximum heating power of
8 MW respectively a maximum absorbed heat of 80 MWs.
The recovery time between pulses at maximal load shall be
20 minutes. Since no deuterium operation is planned during
the first operation period, the TDU can be built from standard
stainless steel. In order to reduce the later effort to
replace the TDU by the high heat flux divertor, all in-vessel
components except the cryo-pumps will be installed from
the beginning on. However, no water-supply will be provided
for the cooling of the in-vessel components except for the
control coils, and some special areas of the wall close to
diagnostics and heating systems. The input parameters for
the design are presently assessed in detail and fixed by a
working group.
Figure 10: Preparation of a wall protection panel for the hot leak test

3.5.1 Target modules
The ten divertor units of the high heat flux target plates are
designed to remove 10 MW convective stationary power
load. Each unit consists of an area of 1.9 m² which is loaded
up to 10 MW/m² and an intermediate area of 0.54 m² which
is loaded only up to 1 MW/m 2 . Each divertor unit is assembled
from several differently shaped target modules. The high
loaded target modules are made up from sets of bar-like target
elements which are supplied by cooling water in parallel and
fixed on a common frame. The supports of these modules
are adjustable within a range of a few millimetres to allow
for compensation of manufacturing and assembly tolerances
of the plasma vessel or uneven heat-loading during plasma
operation. Armouring of the higher-loaded area requires
890 target elements. Their surface must closely follow the
3-D shape of the plasma boundary and will be machined
before assembly of a module. 8 mm thick CFC tiles made of
SEPCARB® NB31, produced by SNECMA Propulsion
Solide, are joined to a water-cooled CuCrZr heat sink.
During the pre-series activities, two types of bonding technologies
were investigated: electron beam welding or hot
isostatic pressing (HIP). The delivered SEPCARB® NB31
material did not meet the specified mechanical properties;
the material was, however, accepted based on the results of
the tests of an additional pre-series. In order to optimize the
manufacturing route and to reduce the stress at the interface
between the CFC and the cooling structure, additional
18 target elements were manufactured by Plansee SE applying
different technologies. The different technologies comprised
the addition of a compliant copper layer between the
AMC ® interlayer and the CuCrZr heat sink by HIP (see
figure 11), the reduction of the size of the CFC tiles to 1/2
and 1/3 of the original tile width, and the rotation of CFC
tiles and hence of the orientation of the ex-PAN fibres by
90°. All these modifications were supported by numerical
simulations. Extensive high heat flux tests in the GLADIS
facility at IPP (see further information in section “Plasmafacing
Materials and Components”) confirmed the benefit of
the introduction of the compliant copper layer whereas the
other modifications did not bring a significant advantage.
However, metallographic examinations of the CuCrZr cooling
structure revealed that a central blind weld between the
cooling channels of the heat sink and the back plate gradually
degrades during the cyclic load tests in GLADIS. This failure
results in a by-pass flow between the cooling channels and
hence reduced heat transfer. As a consequence the design of
the cooling structure was improved and additional eight heat
sinks and ten target elements were manufactured. High heat
flux tests with the heat sinks of this pre-series in GLADIS
were successful; the temperature distribution along the target
elements fully agrees now with numerical simulations.
The procedure for repairing of damaged target tiles shall be
demonstrated by Plansee SE and will be qualified by testing
Wendelstein 7-X
36
in GLADIS in 2008. The results of the high heat flux tests
will also be used to correlate the GLADIS results with the
predictions from infrared measurements carried out in the
ARGUS facility of Plansee SE and in the SATIR facility of
CEA-Cadarache. The correlation shall be the basis for the
acceptance criteria of the target elements of the serial fabrication.
The design of the divertor modules of the lower
loaded area uses graphite tiles clamped on a CuCrZr heat
sink with a graphite paper (Sigraflex) interlayer. Cooling is
provided by stainless steel tubes brazed onto the backside of
the heat sink.
3.5.2 Baffle modules
The baffle modules prevent back-streaming of the neutralised
gas from the target plates. The design uses graphite
tiles which are clamped on a cooling structure made of
CuCrZr. Water cooling is achieved by stainless steel tubes
which are brazed to the backside of the heat sink. The fixing
screws for the graphite tiles are made from titanium zirconium
molybdenum (TZM) alloy. So far about 30 % of the
cooling structures have been manufactured by the IPP workshop
in Garching, and the second lot of graphite tiles has
been ordered.
3.5.3 Wall protection
About 70 m² of the plasma vessel surface is covered by
double-wall stainless steel panels with integrated watercooling.
The second series of 90 panels has been formed by
MAN DWE and is in the final stage of assembly. The channels
within the panels are formed by hydraulic pressing with
approximately 100 bar. In the areas, where ports have been
omitted the plasma vessel will be closed by appropriate steel
plates. Since manufacture of the wall panels is already well
advanced and most of the panels are already in different
stages of manufacture, some areas of the plasma vessel will
not be protected by wall panels during the first operation
phase. During later replacement of the divertor, also some
wall panels have to be replaced in order to also protect the
open spaces. . The inner wall of the plasma vessel is protected
by heat shields. These heat shields use graphite tiles which
are clamped to a cooling structure in a similar same way as
for the baffles. The design has to integrate also several plasma
diagnostic components as well as an NBI beam stopper and
a mirror for ECR heating. By the end of 2007 50 % of the
cooling structures have been fabricated in the IPP workshops.
During steady state and full power plasma operation,
the inner surfaces of the ports need to be protected in the
same way as the plasma vessel. For budgetary reasons, construction
of the port protection panels has been postponed to
a later date. Nevertheless, the design of these protection
elements was continued to fix their interfaces and define the
rooting of the cooling water lines. Since the space behind the
wall protection is very restricted, all port protection panels

will be later supplied from outside. The NBI ports as well as
the port for the diagnostic injector need to be protected
against energetic particles by graphite tiles right from the
beginning on. Due to the spatial constraints these areas need
a sophisticated design. Design studies for both areas have
been started.
3.5.4 Cryo-pumps
Ten cryo-pumps are located behind the target plates and
allow increasing the pumping capacity for hydrogen and
deuterium up to 75 m 3 /s during high-density plasma discharges.
The cryo-pumps are composed of a cryo-panel
cooled with single phase helium, a Chevron baffle cooled with
liquid nitrogen and an additional water cooled baffle. Fabrication
of the cryo-pumps is well advanced (see figure 11).
Figure 11: Main parts of a cryo-pump unit
The cryo-pumps will be installed only after the first operation
phase. Hence fabrication activities were slowed down
and are now only continued in the Garching workshops on a
fill in basis. According to the original design the two pumping
units behind a divertor target would be integrated as one unit
together with the interconnecting cryo-line during assembly
of the plasma vessel. This would have allowed performing a
cold leak-test of the whole unit outside W7-X before assembly.
Since the pumping units shall now be assembled at a
later stage the cryo-line must be separated to allow insertion
of the units into the plasma vessel through a port opening
and joining the cryo-line inside the plasma vessel.
3.5.5 Control coils
Ten control coils will be installed behind the baffle plates.
These coils will be used to correct small field errors at the
plasma edge, to optimize the position and extent of the islands
and dynamically sweep the power across the target plate.
Wendelstein 7-X
37
The coils are supplied by the company BNG. Each coil is
made of eight turns of a hollow copper conductor and is
water cooled. By the end of 2007 all ten coils have been
manufactured and six coils have been tested and accepted
(see figure 12). The first two coils have been delivered to
Greifswald and will be used for assembly trials and a test of
the power supply units.
Figure 12: Functional test of a control coil with integrated current leads
3.5.6 Supply lines inside the plasma vessel
Cooling of the in-vessel components is provided from the
main water system through 80 supply ports in the different
W7-X modules. The interface between the supply lines and
the cooling loops inside the plasma vessel is realised by
plug-ins. The water cooling loops inside the plasma vessel
comprise a very complex network with a total length of
about 4000 m. Routing of the water pipes has to consider the
3D-shape of the plasma vessel, pass around a high number
of port openings for diagnostics and heating systems, take
into account the restricted space behind the wall protection
panels, and identify appropriate attachment points. In addition,
the design of the cooling circuits has to consider many
interfaces with the diagnostics and heating systems. The
detail design of the pipe work is supported by manufacture
and trial assembly of full-scale prototypes of the cooling
loops. First prototype loops have been manufactured by IPP.
Assembly trials are performed in a wooden mock-up of the
plasma vessel which was moved from Greifswald to
Garching.
3.6 Refrigeration System
The refrigeration system has an equivalent peak power of
7 kW at 4.5 K to supply the magnet system the thermal
shields, the current leads and the cryo-pumps with helium
at different temperatures and pressures. Linde Kryotechnik
AG is in charge of the delivery of the helium refrigerator.

The refrigeration process was designed for an operation
scheme where the superconducting coils are energised at
nominal current only during the day. Over night and during
the days of idle operation the plant would run in different
standby modes. To allow economic operation the excess
plant capacity during standby modes is used to liquefy helium
into a 10,000 l storage tank. During full power W7-X operation
helium is taken from the storage tank to boost the
refrigeration power. The change from low-Tc superconducting
current leads to high-Tc current leads reduces the
amount of helium from the storage tank and hence allows
continuous operation of W7-X at nominal magnetic induction.
Such an operation mode is preferred since it reduces
the number of load cycles of the magnet system and hence
the risk of fretting of the sliding support elements between
the non-planar coil casings. The main helium transfer line
between the refrigerator and the magnet valve box has been
manufactured and assembled on site by DeMaCo, a subcontractor
to Linde Kryotechnik AG. This transfer line has a
total length of 54 m and houses 6 supply and return lines
with nominal diameters between 20 and 80 mm. Manufacture
of the two refrigerator cold-boxes, the sub-cooler,
the two compressors, the gas purification system and of the
magnet valve box was finished. After delivery to Greifswald
assembly of the main components and installation of
the warm piping are ongoing in accordance with schedule.
Commissioning of the helium refrigerator will start in early
summer. A software program was developed allowing
simulation of steady state operation of the W7-X refrigerator.
This program models 14 heat exchangers, seven
expansion turbines, two cold compressors, a cold circulation
pump and two screw compressors. The characteristic
parameters of the heat exchangers and the machinery were
adjusted to the results of the main operation modes from
the Linde process layout. This simulation program will be
checked against real operation parameters during commissioning
and allows predicting steady state capacities and
power consumption during later operation. The liquid nitrogen
system of the branch institute consists of a 30,000 l
tank and a distribution system. In 2007 approx. 80,000 l of
liquid nitrogen were provided for the ECRH system, the
cryo-laboratory, W7-X assembly and other users within the
institute.
4 Engineering
The sub-division Engineering (EN) emerged in April 2007
from the former System Engineering (SE) sub-division; it
provides engineering support to the Wendelstein 7-X project.
EN is organized in three departments: Design Engineering
(DE), Development and Test (DT), and Instrumentation
(IN). The report encompasses also the earlier activities in
2007 which were accomplished within the SE sub-division.
Wendelstein 7-X
38
4.1. Design Engineering
4.1.1 Structural analysis
DE continued to investigate the mechanical behaviour of
structural components of W7-X during various modes of
operation. Since the whole structure is by far too complex to
be described in detail by a single finite element (FE) model,
it is necessary to use coarse global and detailed local models.
The latter can be run independently with boundary conditions
extracted from the global models (GM). Two separate
global models are necessary for the whole W7-X basic
machine structural analysis: the magnet system global model
and the cryostat global model. The global models include
elastic material properties only; however, they take into
account nonlinearities like friction and gaps. Theoretical and
experimental crack propagation studies were continued and
different FE-tools were tested for crack evaluation. Steel
casting defects as well as cracks in welds and weld influence
zones were evaluated using analytical and semi-empirical
methods. The latter were also applied for defining weld
quality criteria.
4.1.1.1 Magnet system global analysis
The magnet system GM encompasses the non-planar and
planar coils (NPC and PLC, resp.), the central support structure
(CSS) including the extensions for the coil supports,
and the inter-coil support structure. The latter comprises the
“narrow support elements” (NSE) on the high field side
between non-planar coils, the “lateral support elements”
(LSE) on the low field side between the non-planar coils,
the ”contact elements“ (CTE) between the half-modules and
modules, and the ”planar support elements” (PSE) between
planar and non-planar coils. The narrow and part of the
planar support elements as well as the CTE basically consist
of sliding Al-bronze pads held by steel pad frames, and corresponding
sliding steel counter-faces. The highly loaded
interfaces between the CSS and the coils are provided by
complex bolted and wedged flange connections which partially
open during operation, the so-called central support
elements (CSE). Due to this complexity including many
frictional sliding elements, the magnet GM behaves extremely
nonlinear and is very sensitive to variations of initial
parameters and boundary conditions. In order to get sufficient
confidence in the results, two independent global
FE-models have to be provided. Due to different parallel
developments and special requirements, currently three GMs
are under development and use. They are implemented in
different commercial FE packages: ADINA GM, ANSYS
GM, and ABAQUS GM, respectively. Early versions of the
ADINA GM were for many years the only tools for the
magnet structure design. It is now being recreated from
scratch with partial support of the company IBK. The model
is completely independent from the two others: Contrary to
them, all the coil housing and intercoil support elements are

eing created quite detailed in one piece with contact interfaces
only at places where such ones are also in reality. The
ADINA GM is expected to be the most accurate and fastest.
However, the modelling is not finally finished, the central
support structure including the interfaces to the coil still
have to be completed before an extended test and benchmarking
phase can start. The model is now expected to be
fully operational in the second half of 2008. The ANSYS GM
as the main FE-tool was created in the last years with first
priority with the help of the Efremov Institute. The development
activities, i.e. continuous updating and improvement
of the model, are still ongoing at IPP; however, the contract
with Efremov Institute was closed. Both versions of this GM,
the half module model with boundary conditions representing
the stellarator symmetry (so-called 36° model) as well as
the full module model (so-called 72° model including also
the cryolegs) with cyclic boundary conditions are the workhorses
which are heavily used for all kind of magnet system
analyses. The 72-degree model is applied for analysing
effects which are not in accordance with the stellarator symmetry
like the presence of cryolegs and the dead weight.
However, the module model requires enormous resources.
One run takes typically one week for full load history which
includes bolt preload, dead weight, cool-down, EM force
application, and optionally the effect of winding pack (WP)
embedding. The presence of the cryolegs and the deadweight
result in 5-20 % asymmetry in the displacements
and support forces between neighbouring 36-degree semimodules.
In addition, the rigid body toroidal movement of
the Magnet system is induced by the central structure deformation
and corresponding tilting of the cryolegs. The
ABAQUS GM emerged from a simplified model used for
predicting magnet system deformations during different
assembly steps – the results had to be considered for assembly
procedures and tools. Starting from this basic model it took
relatively small effort by LTC comp. to create a 36° version
of GM in 2006 and a 72° version until the end of 2007. The
model is now installed at the IPP Greifswald and first structure
analysis confirmation runs have been started. The model
benchmarking with ANSYS GM shows good agreement
of the main results. Minor discrepancies are still under
checking and verifications in both GMs. ABAQUS will also
be used for special tasks for which this program is better
suited (e.g. for strength limit analyses which requires elastoplastic
material properties and option of large deformations).The
main GM applications are calculation of main
stresses, deformations and forces/moments in the main
structural elements occurring during different modes of
operation such as bolt tightening already at room temperature,
applying dead weight, cooling to cryogenic temperatures,
and applying the electromagnetic forces. Also the
influences of the winding pack embedding pre-stresses,
different friction factors at the gliding elements, tolerance
Wendelstein 7-X
39
deviations, NSE and PSE gap variations, etc., can be simulated.
The GM is also used for prediction of handling deformations
during assembly. A further application of the GM
was the definition of positions for the mechanical instrumentation
of the structure.
Figure 13: Over-spreading of non-planar coils to install oversized lateral
support block for weld shrink compensation; deformation in mm.
The original study of the Magnet system behaviour and optimization
of the parameters was performed for four main
plasma scenarios with maximum current in different coils,
corresponding to an on-axis field of 3 T. Preliminary analysis
of the remaining 5 operational scenarios reveals that due to the
high nonlinearity of the system some of the supports might
be loaded to the limits already at plasma axis fields somewhat
below the maximal design value of 3 T, therefore the
operation limits in particular for these additional scenarios

have to be explored in the future. In order to reduce the
number of full cycles for the machine, the switch from one
operation scenario to another without unloading to the zero
current has been approved for the project. The corresponding
GM analyses confirm that the main response is within a
5 % range of the previously considered corresponding zeroto-maximum
cycles.
4.1.1.2 Detailed analysis of magnet system components
Using input data from the global models, a number of local
FE models have been developed that scrutinize in detail the
behaviour of the selected components. These local models
were generated and are being refined and updated at IPP
and by other institutes in the framework of international
contracts:
• Forschungszentrum Jülich (FZJ): bus system (ongoing);
• Warsaw Technical University (WUT): central support elements
(ongoing);
• CEA/CRIL Technology (France): central support ring
(contract closed in 2007), coil header deformation (ongoing)
• ENEA (Italy): lateral supports between coils 5-5 (contract
closed in 2007)
• Efremov Institute (St. Petersburg): winding pack analysis
(contract closed in 2007)
Most of the final structural component designs were implemented
in the global and local models. In the course of this
work global and local analyses proceeded iteratively with
design changes until convergence was reached.
4.1.1.2.1 Coils
The updated insulation material properties and GM deformation
data for PLC and NPC winding pack analysis were
collected during 2007 in order to complete the local study
of the most critical WP zones. In addition, a special submodelling
procedure for this task was developed in collaboration
with the Efremov Institute. The conservative consideration
of the coil housing defects as cracks, and fast
crack growth analysis confirm that the accepted defects
investigated so far are tolerable with sufficient margin.
The detailed analysis of the bolted PSEs described below
indicated that the PLC case of type A had to be reinforced
by additional pins. The location and number of pins were
defined, and reinforcements were completed in 2007. The
analysis of coils in self field was performed in order to verify
coil modelling and strain gage measurements at CEA
Saclay. The program to achieve better understanding of
stick slip phenomena and dynamic behaviour of the magnet
system was continued. Dynamic FE studies regarding the
effect of stick slips of NSE and CSE gliding surfaces were
performed internally and with support of KRP and LTC
comps. Further investigations in preparation of the socalled
”MQ-test” (s. below) dealt with the detail impulse
transfer from a pendulum hammer via a steel rod to the coil.
Wendelstein 7-X
40
The design of the trim coils was supported by structural
analysis with finite element calculations.
4.1.1.2.2 Central support structure (CSS)
FE-studies were performed to determine sliding and displacements
of the half-module and module connection
flanges considering a realistic friction factor range. With
these results, the flange shear pins were finally defined, and
the connection bolt loads specified. Some bolts needed to
be modified and re-analysed in order to avoid collisions
with ports. Further analyses were also performed to assess
non-conformities, detail design changes, and weld modifications.
4.1.1.2.3. Cryolegs
A final design change of the cryolegs based on shrink-fitting
the fibre glass reinforced epoxy tube into a steel flange
assembly was proposed, and corresponding design calculations
were performed. Consecutive calculations accompanied
the material development and detail design of the
cryolegs. This work was very time consuming due to the
fact that the 72° GM had to be used in many runs. Towards
the end of the year the final material data were provided by
the manufacturer and confirmed by FE-analysis. The detailed
cryoleg analysis also revealed that one of the cryoleg
support toroidal tie rod could be omitted. Further analysis
work is foreseen accompanying the component test program
and detail design.
Figure 14: Analysis of a cryoleg under design loads

4.1.1.2.4 Central support elements (CSE)
Each coil is suspended on the central support structure via
two bolted connections between blocks as part of the coil
housings, and extensions of the central support structure.
These connections are typically made of a thick single or a
matrix of up to nine long and elastic Inconel 718 rods to
obtain a preload of 650-900 MP a per bolt at 4 K. Stainless
steel wedges are inserted between the coil blocks and the
shoulders of the CSS extension flanges. The wedges, according
to a new design, are welded onto the coil blocks by
two weld seams each (instead of previously one). The detail
analysis continued in close cooperation with Warsaw
University of Technology. Extended models were completed
for the complex triple and double connections NPC2-Z2 +
NPC3-Z2 + NPC4-Z2 and NPC1-Z1 + PLCA-Z1, respectively,
the new weld design for the wedges was confirmed,
and wedge installation procedures were defined with developed
parametric model of typical CSE. The process of
creation parametric models for all critical CSEs is on-going.
The set of such models allows to analyse variation of parameters
(e.g. tolerances) of components like wedges or shims
during assembly.
4.1.1.2.5 Lateral support elements (LSE)
The lateral support elements are located on the low field
outboard side and transmit tensile, compressive and shear
forces up to 1.7 MN, and bending moments up to 200 kNm,
resp. For the non-planar coil pairs 1-1, 1-2, 2-3, 3-4, 4-5 the
limited space permits welded solutions only. For the LSE
between the coils 5-5 at the module boundary a bolted solution
was adopted. The lateral support element weld dimensions
were finally defined, and the basic design of the bolted
LSE 5-5 at the module interface was completed. The functional
specifications were issued. During assembly quick
assessments concerning cracks and material imperfections
were performed which led to continuation of assembly without
significant interruption.
4.1.1.2.6 Narrow support elements (NSE)
The narrow support elements are sliding contacts (~30 per
half module), located on the high field inboard coil side.
They transmit forces up to 1.5 MN between adjacent coils
while simultaneously allowing relative coil movement up to
5 mm when in contact, and relative coil tilting up to
1 degree. In many cases there is a small initial gap in the
range from 0.2 mm up to 4.5 mm between the sliding surfaces
which close gradually during the coil current ramp-up.
The optimization and definition of the NSE gap widths was
an ongoing issue where the analysis results had to be ready
in correspondence to the assembly schedule. On the other
hand, fixing of these sensitive distances was delayed as long
as possible in order to have the most recent FE model and
design updates available. By end of the year this tedious
Wendelstein 7-X
41
work was done and all gaps for the NSEs inside of the halfmodules
were defined. The tilting of the NSE surfaces
against each other during loading adds a considerable sliding-rolling
path length to the pure relative translational coil
shift. Therefore, pre-tilting in opposite direction was introduced
for the NSEs with large tilting angles. The corresponding
algorithm was developed and implemented in the
design and manufacturing procedure.
4.1.1.2.7 Planar support elements (PSE)
The planar supports fix the planar on top of the non-planar
coils. Most of the PSEs are sliding elements with designs
similar to the sliding NSEs, allowing relative coil movements
up to 10 mm when in contact.
Figure 15: Fixed planar coil support elements; stress intensity in MPa
(bolt preload + EM forces in HJ regime)

They have to transmit forces up to 500 kN and to reduce
PLC deformations to tolerable values. A final solution was
found for the fixed supports of the planar coils which replace
one of the previously foreseen sliding elements per coil.
4.1.1.2.8 Contact elements (CTE)
The contact elements are, similarly to the NSEs, sliding
supports between half-module and module interfaces which
transmit compression forces via MoS 2 – coated Al-Bronze
Pads and steel counter-surfaces. In contrary to the NSEs,
the gap width adjustment is possible only after final positioning
of the half-modules and modules, resp., which
requires special provisions. The designs of the contact elements
were finally frozen, and a functional specification
was issued.
4.1.1.2.9 Current lead fixing box
The current lead support structure (“fixing box”) was modelled
and analysed at the IPP, and incorporated in the global
model of the bus-bar system (FZJ, Jülich). The optimisation
of the structure is still on-going.
Figure 16: Analysis of current lead fixing box; deformation in mm
4.1.1.3 Cryo piping
FE-modelling (in ANSYS) of the cryo-pipe work for the
first module to be assembled has started in close cooperation
with the design group. The aim of this work is to determine
Wendelstein 7-X
42
mechanical loads and deformations of the complex piping
system as a consequence of the magnet system movements
during cool-down and magnet excitation.
Z
X Y
Figure 17: Finite element model of cryopipe system for module 5
4.1.1.4 Cryostat
The ANSYS FE cryostat global model refinement and
update in cooperation with IGN and ENEA (cooperation
was closed in 2007) is practically completed, and the model
is operational from the beginning of 2008. The final update
was a consequence of the Scenario 3 implementation which
requests omission of 45 ports. Concerning the improved
horizontal plasma vessel (PV) support system, the common
work of IPP and Rostock University on a procedure for controlled
adjustment and shaping of the plasma vessel within a
range of ±10 mm was completed. The result is an iterative
approach using the algorithm of Rostock and the cryostat
GM of IPP. An accuracy of

Figure 18: Framed outer vessel upper half shell during lifting and turning
over; deformation in mm
injection area for shield design, and AC modelling and simulations
for coil impedance spectrum tests. Under participation
of EN, a project was initiated to create a full magnetic
field model including all uncertainties during the machine
construction and their treatment with a Bayesian approach.
It is intended to accompany all steps of assembly and to
identify critical deviations from the stellarator symmetry in
time and to assess potential correction measures.
4.1.3 Scenario 3 studies
Calculations of different power deposition and cooling scenarios
of the in-vessel components were performed in order
to decide on a simplified design of the Test Divertor Unit
(TDU) and the other components within the PV. As a main
result it was found that under the reduced Scenario 3 performance
requirements a passively (i.e. only radiatively and
Wendelstein 7-X
43
conductively) cooled TDU and liner operation is possible.
Detailed investigations and determination of operational
limits are ongoing.
4.2 Development and Test
4.2.1 Coil support elements
The test program in support of the development work was
basically completed; however, further tests are still required
for final design confirmations, definition of operation limits,
for qualification of new materials, and for preparing decisions
concerning non-conformities.
4.2.1.1 Central support elements
The functional specification of the CSEs was issued, including
the tolerances which sensitively influence the wedge
loads. A special assembly and measurement procedure for
the critical wedges was developed together with the subdivision
Assembly. For those CSEs where flanges open during
operation, a MoS 2 coating procedure was set up in cooperation
with Assembly. Another 3-bolt test was performed.
This full scale mock-up of one third of the critical 3×3 bolt
connection NPC1-Z1 took into account the new wedge
design, wedge welding procedure, the experimentally determined
weld shrink, and the specified tolerances. The counter-surfaces
on the CSS extension shoulders were lubricated
with MoS 2 spray corresponding to the procedure applied to
the NSEs. The cycle number (≈3900 in LN 2 ) and load
sequence was similar to the first test performed in 2005.
However, more elaborate instrumentation was installed in
order to distinguish relevant stick slip events of the sample
from those of the test bed. First stick slips which could be
attributed to flange opening occurred only after 3240 cycles
at 90 % of full load (corresponding to 90 % of 3T-Operation),
earlier weaker acoustic events could unambiguously
identified by triangulation as originating from other parts of
the equipment. At the previous 3-bolt test heavy stick slip
was audible after about 1000 cycles, however, there were no
means to retrace its origin. After both tests the sample
wedges and shoulders showed similar friction traces. Final
conclusions are not yet drawn, the evaluation is still ongoing.
But as a consequence, in W7-X the wedge as well as the
counter-surfaces on the critical CSS extension shoulders
were specified to be MoS 2 -coated.
4.2.1.2 Sliding element contacts
Even though the NSE, PSE and CTE sliding surface coatings
had been decided already, some tests had to be performed
for investigation of manufacture non-conformities,
and clarification of open issues like ageing, break loose,
and tilting effects. For such studies, and since changes and
non-conformities are expected throughout the W7-X construction
period, a setup for scaled down sample tests was
installed at BAM in Berlin. The scaled pads with 23 mm

diameter (instead of originally 73 mm) and a surface curvature
radius of 350 mm (instead of 1100 mm) are loaded with
the same stresses and strains as the full sized ones by applying
only 10 % of the compression force. The scaling is based
on extensive FE calculations. With the BAM equipment,
experiments can be performed much cheaper and quicker as
with the full size samples which were necessary during the
development phase. An additional advantage of the BAM
test bed is its suitability for experiments in liquid helium.
However, for achieving completely realistic environment
conditions, the equipment needs to be upgraded for vacuum
operation at 5 K and 80 K. The tests performed so far did
not completely confirm the previous full scale tests at KRP
which were done in vacuum at 80 K. Surprisingly, no stick
slip occurred during tests in LN 2 up to 15000 load cycles,
but stick slip was immediately present at the experiments in
LHe and ceased after about 50 cycles. This behaviour was
the same for MoS 2 -sprayed and -burnished counter-sides. In
order to clarify this issue tests in vacuum at these temperatures
would be necessary, however, the complete test program
is not yet finally decided. Systematic pad and counterside
MoS 2 layer ageing experiments were started in order to
estimate possible impact of the long exposure to air during
W7-X assembly. In order to reduce such ageing risks, in the
assembly as well as the torus hall the air humidity is kept
below 50 %. NSE pad and counter-side layer application
was supervised, and non-conformities were evaluated as
well as corresponding decisions prepared. In this context a
specification for tolerable defect sizes of sliding surfaces
was created.
4.2.2 Coil quench experiment
Detailed preparation of the intended experiment to mechanically
excite a non-planar coil by hitting it in cryogenic environment
under self-field magnetic load was started after
general consent for such an experiment was achieved within
IPP, with CEA Saclay, and with the coil manufacturer BNG.
The basic experimental procedure was decided, and preparatory
experiments were started. The real mechanical quench
experiment in Saclay is planned for autumn 2008 within an
available time window of the coil test schedule.
4.2.3 Materials
The material data base was maintained and continuously
supplemented as an ongoing activity. Cryogenic tensile tests
of welds and weld influence zones of cold- and warm-hardened
aluminium alloy conductor jacket material were done.
Orthotropic mechanical characteristics (stress-strain as well
as thermal contraction) of fibre-glass epoxy samples of the
bus-bar weld joint insulation were determined at liquid
helium temperature. Microstructure investigations and cryogenic
tensile tests were performed on a new Al-bronze alloy
for NSE/PSE/CE pad material, and further low temperature
Wendelstein 7-X
44
pulling tests on high-quality steel (1.4429 ESU) for highly
loaded NSE pad frames. All these cryogenic tests were carried
out at the FZK. Collection and classification of coil
housing cast defects was almost completed.
4.3 Instrumentation
New strain gauge sensors with reduced temperature dependence
in cryogenic environment were introduced together
with copper plated steel compensation blocks for mechanical
structure instrumentation. This system was tested on
the non-planar coil AAB12 in Saclay and showed good
agreement with predictions from FE-calculations. Instrumentation
of the CSS with these sensors has started. The
extreme mechanical loads on the complex, non-linear magnet
structure necessitate its monitoring during operation. This
information about the mechanical behaviour has also to be
gathered for adaptation of the finite element models to the
as-built material and geometry characteristics in order to
define operational limits of the machine and evaluate possible
abnormal behaviour. An adequate structure instrumentation
concept, based on mechanical analysis results, was
defined. The complete mechanical measurement system
relies upon strain gauges which, besides measuring stress
and strain, will also be used in combination with specially
developed equipment to indicate component deformations
and relative movements. Collision monitoring in critical
areas of ports and the coil header regions will be done
with single contact foils. A strain gauge system including
the corresponding data acquisition equipment was adapted
for dynamic measurements which is required for the
mechanical quench experiment. Much work was also spent
on collection, analysis, and interpretation of strain measurement
results of the CEA Saclay coil tests. This study finally
confirmed the functionality of the pre-existing strain gauges
on the non-planar coils. The suitability of the already assembled
PLC strain gauges, or necessity to exchange them, is
still under discussion, corresponding investigations are
ongoing.
5 Design and Configuration
The subdivision ”Design and Configuration” was established
in summer 2007 to adapt the organisation of the W7-X
project to the increasing assembly activities. In order to support
these activities it was considered necessary to establish
the department ”Configuration Management”. The purpose
of this department was to speedily implement component
changes caused by design changes and to properly keep
track of fabrication errors. In the past some of these tasks
where taken care of within the department System Coordination.
The number of components within the cryostat, the
complexity of their arrangement and the multitude of relative
movements possible in the various operational modes

led to the establishment of the department ”Configuration
Control” whose tasks became to ensure collision-free operation
at all times. These two new departments were combined
with the department ”Design Office” under the umbrella of
one subdivision in order to simplify fast and effective collaboration
between departments that naturally interact
strongly with one another. After about a half year of operation
this organisation has shown its effectiveness in supporting
the device assembly on all aspects by implementing well
defined fast and transparent work flows with a clear distribution
of responsibilities and comprehensive and up-to-date
documentation.
5.1 Configuration Management
The department Configuration Management (DC-CM) plans,
implements and leads the processes that are required to
ensure permanent consistency between the requirements of
the W7-X system specification and the performance attributes
of its components throughout the life time of the
project. The detailed tasks of DC-CM are oriented at the
common standards of configuration management (CM).
CM for W7-X is being implemented with most efficient use
and interlink of existing processes (change request, nonconformances,
interface control, collision control) and tools
(KKS project structure, the PLM-system, data bases).
5.1.1 Change Management
Change Management (CM) controls all change processes,
preserves configuration control at the interfaces, ensures
documentation and consistent implementation in the configuration
of all changes and variances, and provides orderly
communication of change information within the project.
This includes that CM enables change and non-conformance
decisions to be based on the knowledge of complete
change impact. Processes are controlled via a data base.
Highest priority is given to fast handling of change and
non-conformance processes which are time-critical and
might affect the schedule of device assembly. These are
actively guided and driven by CM and thus accelerated.
CM supports preparation and documentation of the configuration
control board (CCB) meetings and the implementation
of its decisions.
5.1.2 Configuration Status Accounting
A PLM-based concept for the W7-X system documentation
has been implemented. It will give access to the complete
configuration information and finally replace the previous
system specification. A central master document for each
W7-X component, the so called loose leaf book, provides
the description of the function of a component and its positioning
in the project structure and the CAD assembly.
Additionally, the loose leaf book is a navigation tool (via
references in the document and links in the PLM system)
Wendelstein 7-X
45
to access specifications, data sheets, interface descriptions,
design changes, and variances that result from non-conformances.
Provision of interface descriptions and accounting
for change impacts across the interfaces is coordinated by
CM. Masses, materials and their composition are documented
for all components within the torus hall in a material
data base. Additionally, the data base documents the certified
relative magnetic permeability of the materials used and
their certified cobalt content as a basis for assessment of
magnetic field errors and to keep track of the amount of
cobalt, which is limited by the authorities due to its high
neutron activation rate.
5.2 Configuration Control
The main missions of the department Configuration
Control (CC) are to ensure collision-free operation of W7-X
for all modes of operation and to coordinate the space
requests of peripheral components in the torus hall and
adjacent buildings. This is being accomplished by developing
the required tools for generating and book-keeping of
the CAD models of the relevant components by performing
the collision checks and finally by initiating and leading the
processes required to eliminate detected conflicts in collaboration
with CM. W7-X is undoubtedly a device with
high geometrical complexity. Especially in the cryostat one
has to deal with three-dimensional free-form shapes of the
coils snugly located between the heat shields of the thermal
insulation of the plasma vessel and the ports, the coil support
structure the meandering lines of the bus-bars and the cryogenic
helium supply, the diagnostic and quench detection
cables and all the required supports and additional components.
Figure 19 illustrates this situation in the cryostat.
Figure 19: Module 5 of the cryostat (outer vessel shell omitted)

Even at room temperature it is already quite difficult to
ensure that none of these components collides with another
since with the used W7-X CAD system CADDS5 only a
small subset of all the components can be studied at one
time. This situation becomes even more challenging if one
wants to take into account the actual geometry of the fabricated
components, the relative movement of the components
under the various loads of operation (configurations),
i.e. baking of the plasma vessel, cool-down of the cryostat,
various magnetic field configurations as obtained from
finite element analysis (FEA). In order to cope with this
complexity the department is organised in three groups that
focus on the development and adaptation of new tools and
the geometrical data handling (Back Office), use these tools
to investigate the components in the cryostat under the
various configurations (Design Space Analysis) and provide
a complete and collision-free reservation of component and
maintenance space in the torus hall (System Layout). In all
these activities CATIA is implemented as the main CAD
tool. Figure 20 shows the data flow between the different
groups and other subdivisions.
FEA
deformation
data
CATIA PLM
export
System Layout
Space reservation,
Torus hall layout,
Collision check
outside cyrostat
Space reservation,
collision checks,
Proposal of routing
Geometrical
measurements
Back Office
Reverse Engineering
Reverse
Engineering
models
CADDS5
Models
(PLM)
Wendelstein 7-X
Tolerances
Design Space
Analysis
Configuration Control
inside cyrostat
Collision reports,
Information for
reworking, etc.
Figure 20: Information flow within the department Configuration Control
46
5.2.1 Geometrical Data Handling
The main mission of the group Back Office is to handle geometrical
data, i.e. to perform ”reverse engineering” activities,
to assess measurement data and to provide measurement
data and results of calculations of movements or
deformations of components to the whole project. The following
tools have been developed:
• data base tools for usage with CATIA,
• tools to automatically migrate the CADDS5 models into
CATIA readable models,
• tool to generate a mirror image of the PLM CADDS5
assembly tree that combines all components of W7-X at
the time of commencement in CATIA format,
• tools to generate CAD “as-built”, “in-operation nominal”
or “in-operation as-built” models,
• Web-based access to the available data-sets in universal
format,
• Web-based overview of the present status of the reverse
engineering process for all components.
Reverse engineering activities led to as-built models of the
planar and non-planar coils, the central support ring, the
plasma vessel and the outer vessel. By using optimised
meshes for as-built models it was possible to drastically
reduce the time needed for the reverse engineering process
from three to one week. This made it possible to further
refine the configuration checks by providing ”as-built inoperation”
CAD models.
5.2.2 Design Space Analysis
The main mission of this group is to perform configuration
checks of the components in the cryostat to ensure collisionfree
operation. The various configurations considered are
room temperature, cool-down to 4 K, baking of the plasma
vessel and ports at 150 °C, deformation of the coils for 3 T
operation and magnetic configurations standard, low shear,
low iota and high iota. To this purpose the distances of the
considered component to all the neighbouring components
are measured. With the help of CATIA it is possible to automatically
ensure that all near-by components are taken into
account. These distances are evaluated on the basis of the
known or estimated fabrication tolerances, assembly uncertainties,
adjustment regimes and calculated deformations.
Component changes are initiated if collisions are likely.
With the help of the tools made available by the ”back
office” it was possible to increase the accuracy and completeness
of the assessment by replacing the CAD models
with as-built models (if available) or use models that mimic
the calculated operational deformation. The results are documented
in collision reports that then form the basis of design
changes or component changes. In 2007 about 200 collision
reports were issued for e.g. the planar and non-planar coils
of module 5, the central support ring, the port cryo insulation,
and the bus-bars.

5.2.3 Torus Hall Layout
The main mission of the system layout is to provide and document
the space reservation of all the components outside of
the cryostat in the torus hall and adjacent buildings. CATIA
was made the principle tool also for this task. Based on a
discussed and established priority list of the components in
the torus hall the component volume and maintenance space
is systematically being checked and if necessary modified to
meet all requirements: sufficient volume for the component
with some margin for design changes and accessibility for
maintenance and repair. In case of conflicts or if design
changes are required the system layout group organizes and
moderates the required meetings amongst those affected and
takes care that the decisions are properly implemented.
5.3 Design Office
With the foundation of the subdivision ”Design & Configuration”
also the department Design Office (DO) was
restructured. The tasks of the Design Office are developing
design solutions and providing fabrication drawings for
components, supports, and tools for W7-X in close cooperation
with responsible officers in other departments. Additional
tasks are defining and implementing design guidelines
for working with CAD programmes and maintaining a
proper structure of the CAD models in the data base. The
numbers of designers had to be increased in order to cope
with the additional tasks. Those tasks arose when originally
externally designed components were decided to be designed
in-house or when the challenges in finding design solutions
proved more time-consuming than originally estimated. In
order to accomplish these tasks the design office is organized
in four design groups that focus on those areas with
most design activities: structural components in the cryostat,
supply components in the cryostat, components in the plasma
vessel and diagnostic components. Each group has a technical
group leader (or the head of the design office) who
coordinates the work, maintains the design standards and
provides the project with an overall view of what additional
resources are needed to accomplished the still outstanding
design activities. Care is taken that for particularly timecritical
design activities a sufficient number of properly
trained designers is available. The main CAD tool of W7-X
is CADDS5. Good progress has been made to update and
properly position all models and components of W7-X in
the CAD documentation system in the CADDS5 format.
Since in the future the need may arise to use the same CAD
tool as ITER, CATIA V5, a number of projects with well
defined geometrical interfaces (stored in CADDS5) are
being designed in CATIA V5. This also facilitates to gain
experience, create nucleation points for information transfer
and allow external personnel to be hired since the usage of
CATIA V5 is more widespread than CADDS5. Simultaneously
the performance of various CAD storage systems
Wendelstein 7-X
47
for CATIA V5 is being analysed. The group components in
the cryostat focussed on the following tasks: The plasma
vessel CAD models were adjusted to take into account the
latest design changes. The CAD models of the lateral support
elements, that are typically U-shaped structures welded
to the coil housings of adjacent coils on the low field side,
were completed and detailed manufacturing drawings were
provided based on the on-site measurements of the distances
between the coils. The design of the cryostat legs was modified
to incorporate a GFK rather than a stainless steel tube
and the manufacturing drawings were completed. The group
cryostat routing focussed on generating a set of models of
the helium supply lines, supports and cryo shields of the
outer vessel in module 5 of the cryostat that is able to cope
with the increased stresses during the relative movement of
the components during operation. Collision-free design under
all configurations is achieved in close collaboration with
Configuration Control. The group components in the plasma
vessel focussed on completing the detailed design of the
housing of the diamagnetic loops, the model design of the
water supply lines to the wall panels, baffle and targets, the
manufacturing drawings of the wall panels. Various iterations
were necessary in particular for the water line routing after
some significant design changes had to be made as a result
of insufficient installation space. The group diagnostics
focussed on those components that are to be installed earliest
within the assembly schedule. These are the Rogowski coils,
the Mirnov coils, the bolometer, the diamagnetic loops, the
neutral gas manometer and Thomsen scattering.
6 Assembly
In 2007 the preparation of the assembly sites, the assembly
equipment, and extensive assembly trials have been continued.
An additional assembly area (storage and preparation
hall in Lubmin) was rented. Contracts for the design
and the procurement of further complex assembly devices
(assembly bridge, vessel rigs) have been launched. The
mounting stands III and IV were delivered and installed as
planned. The manufacturing of the bus-bars (cooperation
with FZ Jülich) was continued; the first set of conductors
was delivered to Greifswald, the manufacturing pre-requisites
for the mechanical supports of the bus-bars were further
developed. The preparation of plasma-vessel sectors and
coils was continued as planned. Two half-modules are almost
completely assembled in both mounting stand MST I and
MST I b. Expensive assembly trials have been performed to
ensure the mounting accuracy of magnet modules in the
final assembly. Special welding procedures for the LSE
welds with minimised shrinkage were finished. Several new
engineers and craftsmen started their work. The assembly
process-planning, process documentation and work safety
system run furthermore reliably.

6.1 Bus-bar System
The manufacturing of bus-bars continued. The first set of
conductors for the first module was delivered. The manufacturing
of bus-bars runs routinely. The design of mechanical
supports for the bus-bar systems has been further
developed. The associated drawings are partially approved.
Supports had to be redesigned since several clashes with
surrounding components were detected. Assembly tests
with dummy bus-bars were successfully made together
with FZJ. Technicians from INP in Krakow were trained for
the bus-bar installation. The joint-prototype test at the
Efremov Institute was completed. The welding procedure
for the bus-bar joints is finished. Practical installation exercises
have started under real on-site conditions. Construction
works for the current lead joint-prototype were continued.
First practical works with dummies are made. These
works are continued in 2008. The specification for the
wiring and insulation of the quench-detection system was
further developed. The qualification and delivery of insulation
parts was contractually bound. Some difficulties arose
at the manufacturer with respect to the proper handling of
the rather liquid resin.
Figure 21: 1st set of bus bars in the bus bar preparation area
The bus-bar preparation was set-up, all tooling and rigs
were provided and installed. Additional engineers and technicians
from INP in Krakow will be trained and integrated
into the bus-bar assembly team. Again problems with the
aluminium welds at the coil terminals occurred. Small
cracks at production proof samples were detected. The
welding process was refined, however, the limits of feasibility
have already been achieved. In terms of the assembly
schedule more bus-bar works were moved to the preparation
phase; away from the critical path. As a result additional
assembly works on the bus-bar system can now be carried
out without influencing the overall project time plan.
Wendelstein 7-X
48
6.2 Vacuum Technology
The work packages of the vacuum technology group in 2007
were continued as in 2006. Main tasks were: leak detection
on single components and monitoring of leak tests at suppliers
(Tesla, Ensa, BNG) as well as leak and Paschen tests
on coils and on cryo piping of thermal insulation during the
coil preparation and assembly. The works at Tesla were
finalized at the end of 2007. Local leak tests with diverse
test chambers for superconductor connections and cooling
pipes at room temperature and at 77 K (if technically necessary)
are routinely implemented during assembly. The design
of these test-chambers as well as the qualification of the
tests was further continued. Qualification tests of materials
and devices concerning the suitability in vacuum (outgassing
rates, Paschen stability) were realised in a laboratory.
Little progress was achieved on the specification of the
vacuum systems since it depends on the progress of the layout
in the torus hall.
6.3 W7-X Assembly
The work in the component preparation, especially on coils
and plasma vessel sectors, has been continued as planned.
Components for the second module are being prepared. The
works are running routinely. The scope of scanning works
on these components was considerably extended. As a result
additional external resources had to be hired. Additional
storage capacity for prepared components outside the institute
was refurbished and put into operation.
Figure 22: PV sectors during the test assembly – rigs are sliding on air
cushions
Additional staff was hired to cope timely with the expanded
preparation works. There were, however, hardly any technological
changes in the coil preparation. Therefore, one can
consider the qualification of the coil preparation as completed
from today’s point of view. With respect to the preparation

of plasma vessels difficulties arose. The preparation of three
dimensionally bent cooling tubes turned out to be quite timeconsuming
due to very restricted tolerances. Special procedures
and tooling were developed to cope with the situation.
Concept works have started to establish an effective procedure
for the closure of the openings in the plasma vessel.
The openings are caused by the omitted 45 ports. The preparation
work on the ports was continued in an external hall.
The scope of incoming inspections at ports had to be considerably
extended since many unexpected contour and
position deviations were found. A special soldering-process
was developed to connect ports with copper foil. This shall
guarantee the demanded cooling qualities of ports.
Figure 23: Incoming inspection of ports
The two first half modules are built up in the pre-assembly
in the mounting stand Ia and Ib as planned. It is expected
that they are ready at the beginning of March. The assembly
area for the subsequent connecting into modules is already
prepared. The assembly of segments of the central support
ring ran as planned. No severe technical problems occurred.
The tightening of bolts and SUPERBOLT nuts worked without
problems. The welding of lateral support elements was
materialised with the expected high accuracy. Many lessons
were learned within the last months in which the assembly
speedily went forward. Extended working times in two shifts
and additional personnel were used to meet the challenging
assembly schedule. The cooperation of the different departments
at the assembly worked exemplarily. Corrective actions
for deviations in quality were immediately decided with the
help of the configuration control board. The next main step
is the start of the module assembly within the pre-assembly
phase. Particularly the joining of adjacent central support
ring segments requires further qualification. In that context,
practical tests with reaming tools have been performed in
2007. They will be continued within the next months.
Wendelstein 7-X
49
For the second module the preparation of separation planes
of plasma vessel sectors was jointly made with MAN DWE.
The assembly equipment and the accompanying processes
worked as planned. A special challenge in that phase will be
the assembly start of the bus-bar system, the helium piping
and the module instrumentation.
Figure 24: Trial threading with M76 bolt
The set-up of mounting stands III and IV in the torus hall
were successfully completed in 2007. Tests showed that the
systems work as designed and without any inadmissible
deviations. A very complex alignment test was made by the
use of MST IV simulating the final adjustment of 100 t
modules within an adjusting range of +/-5 mm in all three
directions. The test preparation was extensive and lasted
about half a year. The test equipment was timely delivered
by industry. At the end it was shown that the alignment
worked as planned with accuracy far below 1 mm, i.e. much
better than planned. Problems with the electrical insulation
of the machine base (grounding) were successfully solved.
Works were continued for the assembly conception of outer
vessels. It turned out, that the needed assembly equipment
will be much more complex than expected. First parts of
that equipment were designed and ordered in 2007. The
design works were assisted by colleagues from PAS in
Krakau. This work is time-critical and is continued with
additional resources in the year 2008. It also turned out that
the thermal insulation of the outer vessel shells is much
more time-consuming than planned and that it requires
much more space than originally available. It became necessary
to hire an additional hall – large enough to store 8 to
10 shells and to allocate the workplace for the insulation
works. A hall was found at a distance of 30 km and the renovation
work has already started. It is planned to start the
preparation works at the first outer vessel shells in the early
summer of 2008. The ramps and the bridge for the port

installation were ordered in industry. As usual, the detailed
manufacturing design was much more challenging than
expected but the procurement of these devices is presently
within schedule. The first delivery of these devices is
expected for the middle of 2008. The installation procedure
for ports was further refined in 2007. Particularly for special
(non standard) ports these works have to be continued in
2008. In addition welding tests were started to develop first
procedures for the joining of port to the vessels. These tests
are continued in 2008.
Figure 25: Trial alignment with 100 t-dummy load
The cooperation with the colleagues from IPP Garching in
the field of conceptual planning of the assembly of the KiP
has been continued in 2007. First assembly equipment for
in-vessel components was designed, provided and tested in
the assembly area. Systematic investigations for interactions
of the different tolerances and deviations on the components
of the cryostat during manufacturing and assembly were
carried out. With the periphery, the work on cryo instrumentation
has been further continued. Due to clashes of the helium-piping
with other components the routing of the cryo
instrumentation was redone. A simplified system of holders
and mechanical supports was developed to speed up the
installation of the instrumentation. The design for the first
Wendelstein 7-X
50
module is available. First components have already been
qualified. Installation works of the extension of the low
voltage power supply system have started. The work runs as
planned, the earthwork foundation is completed. Detailed
planning of the concept of the grounding area in the torus
hall and diagnostic was continued. The high rack for the
control unit was mounted as planned and without any
inadmissible deviations. The first construction stage of the
cooling system was started in 2007. These works are ongoing
as planned. The assembly control and planning work
reliably as before. Additional resources have been allocated
to cope with the increased work load. The weekly and
4-weekly plans identify necessary handover dates for components
for assembly so that the other subdivisions and
departments are able to provide the necessary information
and make appropriate decisions. The preparation of the
assembly documentation (QAAP, work and test instructions)
is ongoing without any severe problems. In 2008 the daily
planning will be refined to improve the utilisation of resources.
A system was implemented to monitor the consumption
of resources. That system will be further completed in
2008. Quality deviations are reliably recorded and monitored.
The fast preparation of effective corrective actions by
the causer of a quality deviation has to be improved. The
nomination of a Configuration Control Board improved the
effectiveness and speed of decisions which are caused by
quality deviations. The complete assembly schedule and the
plan of resources were again extensively updated and optimised
in detail. The effect of the delayed component delivery
and the additional assembly work were considered in updated
milestones. Contingencies were included to cope with
yet unknown assembly technologies. Additional personnel
recourses for assembly have been included (metrology,
mechanics). Three additional responsible officers (final
assembly supervision, planning, and KiP) took up their
employment. More external staff was included to man the
two-shift system and the extended working times in the
assembly. Additional engineering staff started work for the
procurement of the extensive assembly devices of the outer
vessel. A cooperation with engineers and technicians of the
Polish Academy of Sciences has started. A detailed planning
for an accelerated assembly schedule was carried out. The
increase of the working time per week, a reduction of the
amount of components to be assembled as well as the availability
of additional assembly equipment are the essential
changes in that updated plan. The expected date of the start
of commissioning of W7-X is now in mid 2014. Altogether,
assembly has reached the planned progress in 2007. Several
new assembly technologies were qualified and successfully
tested. The assembly technologies for the preparation of
coils and plasma vessels as well as for the mechanical preassembly
of modules were defined. Particularly in the second
half of 2007 the device assembly ran continuously and

speedily as planned. Additional resources for engineering
tasks and additional technicians for assembly works were
hired to cope with the challenging schedule. Additional
storage and preparation space was procured and refurbished.
New work packages for the technology development of the
final assembly were launched. The purchasing of the peripheral
hall equipment (cooling circuit, electronics, vacuum,
etc) occurred as planned. In 2007 the weekly working coordination
was complemented by daily co-ordinations. Up
to now, there are approximately ten companies and partnerinstitutes
which provide skilled and well-trained technicians
and engineers for the realisation of the assembly work on
W7-X. That cooperation works well. In 2008 further companies
shall be qualified in order to meet the increase of personnel
required by the subdivision Assembly.
Figure 26: The almost completed half modules Ia and Ib
7 Diagnostics
7.1 Overview
The work concentrates on the ”start-up diagnostics” set
necessary for safe operation and control of the machine and
those diagnostics adapted to and being indispensable during
the initial operation phases of the experiment. Time, financial
and manpower planning is adjusted to the agreed modified
time schedules of the W7-X assembly. The diagnostics
project/department is divided into nine expert groups and
groups on technical coordination, documentation and control.
A temporary working group within the project covers
R&D on the development of heat-resistant plasma facing
optical components.
7.2 Reports of Expert Groups
The following sections briefly summarise the main activities
within the expert groups of the project. Due to assigned
Wendelstein 7-X
51
priorities there were no activities in 2007 in the subgroups
on fluctuations, fusion products and heavy ion beam probe
and fast particles.
7.2.1 Edge and Divertor Diagnostics
The activities regarding the divertor thermography system
focused on basic investigations of the temperature enhancement
and its temporal evolution at surface heat loading of
contaminated CFC-surfaces. The measured surface temperature
excursions have been compared with values of analytic
and numerical solutions of the heat diffusion equation taking
into account a surface region with low thermal conductivity
or poor thermal contact to the underlying substrate material.
Collisions of the pop-up arrays and its drives with divertor
structures have been eliminated and the complete routing
for all media (electricity, pressurised air) of one pop-up
array was carried out including mounting and welding
aspects. The set of manufacturing drawings was completed
further. Following the idea of exploiting the same probe
array for the Test Divertor Unit (TDU) and the High Heat
flux Divertor (HHD) and as a consequence of the different
bending of the target elements under thermal load a completely
new concept for the pop-up Langmuir probe arrays is
envisioned. This should allow for an independent motion of
the individual probe together with a local placement with
respect to the target surface. An attempt will be made to
move over from a pneumatic to an electric drive to get rid of
the pressurised air. First manufacturing drawings of manometer
cannulae are produced and three flanges for prototypes
are manufactured and completed with feedthroughs
and welded signal cables. Two of those passed the vacuum
leakage tests. A final design of the screens against electromagnetic
disturbances was completed. The semi-finished
parts for the cannulae have been selected and the manufacturing
drawings were adapted to this selection. As the result
of several tests of the manometer electronics we decided for
one type of power supply for the manometer heating and
ordered those supplies. Several measures to reduce the
observed noise in the manometer signals are being discussed
and investigated. This activity is still ongoing.
7.2.2 Microwave Diagnostics
For the first experimental campaign of W7-X the group
prepares the multi-channel ECE radiometer, a basic version
of the multi-channel Mid-Infrared Interferometer dedicated
to cross calibration of the Thomson scattering and density
feedback control and a single Interfero-Polarimeter channel
to ensure redundancy of the latter. Preparative work
for Reflectometry is also conducted. According to schedule
the main design activities were related to in-vessel components.
A basic design for interferometry retro-reflectors
which have to be integrated into the first-wall heat shield
was developed together with the Dutch company TNO.

FE calculations show that the degradation of the optical
specifications resulting from high heat loading during 30 min
discharges can be minimised by constructive measures. A
PhD thesis on the optimization of sightline geometry of the
multi-channel interferometer was finished. In the laboratory
the optic design of the prototype two-frequency CO 2 -CO
laser interferometer has been improved. On focus were
mode purity, the development of a single detector design
and the minimization of crosstalk. The cooperation with
CIEMAT (Madrid) where a CO 2 -YAG system is operated at
the TJ-II stellarator continued. A two frequency arrangement
with wavelength combination of 10 μm and 5 μm is necessary
to cope with vibrations and thermal drifts of the optical
path length during the discharge. An interesting alternative
for steady state devices could be dispersion interferometry
where the second required wavelength is obtained by frequency
doubling in non-linear crystals. A prototype system
is being operated at the TEXTOR tokamak. Its steady state
capability and extension to a multi-channel system is being
investigated, finally aiming at a quantitative comparison of
both alternatives. Preliminary studies for electron density
measurements by Polarimetry in the complex magnetic geometry
of W7-X were conducted in cooperation with the
Akademia Morska, Szczecin, Poland and the Technical
University of Szczecin. Main topics were the minimization
of spurious polarization changes introduced by the unavoidable
retroreflector behind the plasma. In the framework of
the European Fusion Training Scheme (EFTS) a training
program Microwave Diagnostic Engineering for ITER
(MDEI) has been proposed together with IST Lisboa, CEA
Cadarache, and CIEMAT Madrid. Approval was in July. The
trainee program started at IPP Greifswald in November with
test measurements on the W7-X multi-channel ECE system
and design work on ECE in-vessel viewing optics. For
Reflectometry preparatory work on in-vessel components
and transmission lines is continued to ensure the availability
of this diagnostic for the characterisation of edge density
profiles in divertor relevant W7-X scenarii. As a basic component
of the W7-X Diagnostics Project, the Microwave
Stray Radiation Launch facility (MISTRAL) has been installed
at IPP Greifswald. Starting from March 2008 diagnostic-
and other in-vessel components will be tested in this
test facility in the environment of continuous isotropic
140 GHz radiation as expected also in certain ECRH-heated
scenarios.
7.2.3 Charge Exchange Diagnostics
The group is developing the Russian Diagnostic beam
(RuDI-X) needed for active CXRS and CX-NPA measurements
in cooperation with FZ-Jülich and the Budker-
Institute of Nuclear Physics (BINP) Novosibirsk. The latter
has continued the construction of the HV power supply
(60 kV, 10 A). The tests of RF and ion arc sources at the
Wendelstein 7-X
52
diagnostic beam at TEXTOR are finished, favouring the
RF source for RuDI-X. Infrastructure work (cooling water
supply, power supply, collision studies, etc) for the installation
of the diagnostic beam was continued. The high voltage
transformer for the injector has already been installed in the
operating lab. It has been decided to use a closed circuit
cryogenic pump systems, directly connected up to the neutraliser
chamber, rather than a LHe bath system. Reports on
the status of RuDI-X were presented by participants from
BINP, FZJ and IPP-MPG in a meeting in Greifswald from
18.-20.08.2007. For CX-NPA measurements a set-up of one
Compact Neutral Particle Analyser (CNPA), two ACORD-24
and one ACORD-22 analyser is foreseen. The CNPA has
been tested on MAST at the Culham Science Centre showing
results which are in good agreement with results of the
Princeton analyser. The IOFFE Institute St. Petersburg has
started with the conversion of a 10 channel analyser from
W7-AS into an ACORD-24 analyser. The completion of this
analyser upgrade is planned for September 2008. It will be
used in the calibration laboratory for the NPAs which is
presently being set-up at IPP Greifswald.
7.2.4 Spectroscopy
The test operation of the high-efficiency XUV overview
spectrometer system (HEXOS) installed on TEXTOR (FZ
Jülich) has been continued successfully. VUV/XUV spectra
were recorded with high time resolution (1 ms) over the full
duration of almost all TEXTOR discharges in 2007, thereby
demonstrating a full coverage of all prominent impurity
lines with high availability (>98 %) and good spectral resolution.
An intensity calibration of the HEXOS spectrometer
channels was performed and a variety of transient impurity
transport experiments (fast Argon puffing) were conducted.
The hardware assembly of the remote control system is
completed and the programming is in progress. The cooperation
between IPP and the University Opole (Poland) concerning
the development of a C/O monitor diagnostic for
W7-X has officially been started and a work break down
schedule agreed on. The basic design was fixed and various
options for detectors are presently under discussion. For
selection and test of appropriate detectors, crystals and calibration
sources the W7-AS crystal spectrometer was transferred
to and reassembled in Opole. For achieving sufficient
bolometer sightline coverage of the plasma cross section for
tomographic inversion, the observation gap in the baffle
structure for the divertor bolometer in front of the AEJ40
port has been enlarged and the diagnostic design for the
enlarged cut-out been finished. For the bulk plasma bolometer
system in the triangular plane the design of the sightlines
of the AEU30- and AEV30-camera has been completed.
The camera in the AEU30 port possesses 32 up/down
symmetric channels, collimated by one slit-aperture. The
camera in the AEV30 port contains two detector lines of

20 channels each which are collimated by two separate slitapertures
in order to achieving the required wide viewing
angle view. A first design of the water cooled aperture plate
and detector holder has been completed. FE calculations
(ANSYS) of these designs are presently being performed
to evaluate the temperature of the camera components for
W7-X steady state operation conditions (~50 kW/m 2 ). A
study of the neutral pressure sensitivity of the metal foil
detectors has shown that blind-channels need to be integrated
into the design of the bolometer cameras to monitor this
effect. The detailed design of the video diagnostics – which
is being developed by KFKI-RMKI Budapest – was finished
in 2007. For the video observation the 10 equivalent
tangential AEQ-ports of the W7-X vacuum vessel will be
used giving nearly full coverage of the entire plasma vessel.
In the elaborated design the Sensor Module (SM) of the
Event Detection Intelligent Camera (EDICAM) is located at
the plasma end of the ports. The mechanics that transports
and docks the camera capsule – containing the SM to the
front window was manufactured and its mechanical and
thermal tests will be completed in 2008. Also the design of
the diagnostic front end, consisting of an air – vacuum
window, a small shutter and a water cooled plasma facing
front plate with a pinhole for plasma observation has been
completed by IPP Greifswald. The manufacturing of the
prototype is still ongoing. Radiation resistance test had been
performed on the first version of the Sensor Module. The
current version of the SM consists of only the essential electronics
in order to allow testing the performance of the
CMOS sensor itself, without the possible influence from a
more complex electronics. The SM was irradiated at different
gamma (between 0.1 Gy/h and 5 Gy/h) and fast neutron
(between 0.7 Gy/h and 1.4 Gy/h) dose rates in fission
research reactors. The evaluation of the images obtained
during the gamma irradiation test shows no enduring damage
on the CMOS sensor. Gammas cause only short time
flashing of the effected pixels. During the neutron irradiation
test the SM absorbed about 60 Gy total dose (about the
quadruple of the expected upper limit of the annual dose at
W7-X) revealing a clear increase of the dark current of the
individual pixels with increasing accumulated dose, but it
still remained functional. The development of the EDICAM
Image Processing and Controlling Unit (IPCU) and 10 Gbit
fibre link connecting the SM to the IPCU advances according
to the plans. The hardware kit for the IPCU (FPGA development
board with PCI express PC connector, ALTERA)
was purchased. The 10 Gbit fibre link is expected to be ready
in 2008.
7.2.5 Thomson Scattering
The design of a polychromator prototype for analysing the
scattered light was continued and successfully tested at
ASDEX-Upgrade. A water cooled shutter was designed, to
Wendelstein 7-X
53
protect the vacuum window in front of the observation port.
A design study for the observation optics has been performed
with the optical design program ZEMAX.
7.2.6 Soft X-Ray and Magnetic Diagnostics
The design for the integration of the in-vessel X-ray tomography
camera system (XMCTS) beneath the heat protection
roof (designed by KiP) has been finalised. The camera
design including the cooling is completed and finite element
calculations were performed proving the effectiveness of the
cooling with respect to the expected heat fluxes. Several
components for the XMCTS are being manufactured for
prototype testing. Notably, the vacuum feed-through connectors
between the photo diode array and the electronic
box have been designed and manufactured by the company
Schott. The shutter prototype (protecting the photo diodes
during glow discharges and allowing for offset drift correction
during long discharges) was tested. Its mechanical
design is based on a pressurised manometer tube spring
attached to a lid. It was demonstrated that the shutter is
capable of more than 100,000 cycles under vacuum conditions
with additional heating cycles. The robustness of the
design is therefore sufficient, but small improvements are to
be considered for optimal operation in the W7-X vessel. The
continuation of the work on the preamplifiers was very difficult
throughout the year due to the lack of manpower in the
Greifswald electronics department. The cross-talk problem
between channels has been overcome to a large extent. One
of the main tasks in 2008 will be the test of a preamplifier
board fitted into the vacuum-tight electronic box. Further
major tasks in 2008 are the in-vessel cable routing and the
assembly of a prototype camera. The legacy code for the
tomographic inversion of W7-AS SX-ray data is being ported
from a specific AIX/W7-AS environment to a general Linux
version, which will be advantageous with respect to the
processing speed and portability. The code was simplified,
generalized and optimised and converted to a more consistent
and object-oriented design. The long discharge
lengths of W7-X pose a severe challenge to the data analysis
task. The amount of data from the XMCTS system in continuous
acquisition for a 30 min discharge sums up to about
500 GBytes. A method for an online method giving information
on the plasma shape and possibly mode onsets on a
human time scale is desirable. One approach to this challenge
involves the application of neural networks, which are
real time capable after a time-consuming training phase.
This work was done in collaboration with IST and IPP
Garching. First results were presented on the Plasma 2007
conference. The collaboration contract with the IPPLM in
Warsaw on X-ray pulse height analysis and on an electron
temperature monitor system based on the filter foil method
has to be extended. The main focus in 2007 was on the layout
of the filter system and on suitable data analysis algorithms.

A major task in 2008 will be the choice and procurement of
a detector for X-ray pulse height analysis which will be
tested at IPPLM. The magnetic diagnostics has been further
constructed and manufacturing processes have been qualified.
The first Rogowski coil in module 1 has been successfully
tested. The tests have been performed by using a cable
that is fed through the small sector of the plasma vessel, on
which the coil has been installed. This cable represents a
localised plasma current and has been supplied with a current
of 200 Amps. The induced voltage has then been integrated
using the original prototype digital integrator running
under Linux. The results are very promising with respect to
integrator drift values in the envisaged steady state discharges.
The measured drifts are the order of 1 Amp. per
minute discharge duration. The design of the diamagnetic
loops has almost been completed and the concept of the loop
fixation has been worked out. The manufacturing of the
100 pin connector has been qualified for connecting the
Kapton insulated ribbon cable in order to form the electrical
loop of at maximum 100 windings. Additionally, a second
small prototype loop has been built and is ready for dedicated
ECRH stray radiation tests with several different
microwave screening materials. The installation of the saddle
loops has been continued, that is module 1 has been fully
equipped with all 8 loops. Furthermore, a first routing of
saddle loop signal cables in the warm region of the cryostat
along the cooling pipes of the plasma vessel has been
realised in module 5. The cable routing of all magnetic diagnostics
is under revision due to the cancellation of a number
of ports. One complete system of 10 identical ports is omitted
entirely, which had originally been assigned for cable
feed through. Thus, re-routing has become necessary and
substitute cable paths are currently under investigation.
7.2.7 Diagnostics Software
7.2.7.1 Physics Data Repositories
The development of data repositories for preparation of
W7-X was continued. The “Reference Database” was filled
with predictive calculations from neoclassical transport
simulations. These simulations cover ECRH and NBI density
and power scans for different magnetic configurations.
The parameter range is continuously extended. The structure
and general policy of the international Stellarator/
Heliotron profile database was discussed and agreed with
the collaborators.
7.2.7.2 Software Development Infrastructure
Central software repositories were provided for routine
work in the W7-X Project and for physics codes. A WIKI
system – also hosting the Reference Database – was set up
and is employed for diagnostics development communication
(in cooperation with RZG). A reference server for
integration purposes was set up. Software standards were
Wendelstein 7-X
54
assessed in order to develop a software quality management
(in collaboration with W7-X QM).
7.2.7.3 Integrated Data Analysis and Diagnostics Design
Efforts on Integrated Data Analysis were continued in collaboration
with ASDEX Upgrade. A simulation code for
video cameras was developed. An XML-schema for the
parameter description in simulation of the tomography was
developed. The case study for the interferometer design
were finished and documented. The software support of the
design of the polychromator system was finished and documented.
The analysis of spectroscopic data was continued
and first results for the reconstruction of electron energy
distribution functions were obtained. (Cooperations with
W7-X Diagnostics and ASDEX Upgrade).
7.2.7.4 International Stellarator/Heliotron Confinement and
Profile Database
Within an international collaboration (IEA implementing
agreement) the International Stellarator/Heliotron Confinement
and Profile Database was continued and extended.
Comparative Studies on impurity transport, divertor physics,
energy confinement, neoclassical effects were performed
and documented (NIFS, CIEMAT, University of Kyoto,
ANU, University of Wisconsin, PPPL, University of Stuttgart).
7.2.8 Technical Coordination
The assembly of the first outer Rogowski-coil has been
completed by making the electrical contacts, measuring the
induction and mounting a temporary shield. The saddle coils
on the two larger half sectors of the half modules 10 and 11
were assembled in time before the assembly of the thermal
insulation. To denominate the diagnostics according to the
prescribed KKS-system, the aggregate key was extended.
The requirements on the materials used for the video cameras
were specified and relayed to the cooperation partner, the
KFKI-RMKI institute in Hungary. The signal exchange
between the EDICAM camera and the W7-X control and
data acquisition system was discussed and the further course
of action agreed on. A working group was initiated to deal
with the requirements on weld seams in the diagnostics.
Layouts for the west and for the south part of the first basement
of the torus hall were drafted that now include all
necessary support structures of the components that are
positioned above these areas. The data on the fire load of the
diagnostics in the torus hall have been collected.
7.3. Collaborations
The diagnostics are being developed in close collaboration
with FZ-Jülich. In particular in case of the HEXOS VUV
spectrometer and the development of the diagnostic neutral
beam FZ-J is heading the projects. The Budker Institute in
Novosibirsk, Russia, is developing and constructing the

diagnostic neutral beam injection system, KFKI/RMKI in
Budapest, Hungary, is developing and constructing the
video diagnostic systems for W7-X, IPPLM, Warsaw is
developing a neutron activation system and performing
MCP calculations for W7-X, the university of Opole (Poland)
is preparing a C/O monitor diagnostic and the Akademia
Morska, Szczechin and the Szczechin University of Technology
are investigating the sightline of the Interfero-
Polarimeter and different microwave based polarimeter and
interferometer methods, CIEMAT investigates potential and
components for CO 2 -Intefererometry, IST participates in
developing fast tomographic inversion methods (P. Carvalho
4 Months stay in Greifswald) and is developing ADC/DAQ
stations being linked to XDV, PTB, Braunschweig is performing
preparatory work for a contract on the development
of a Neutron-Counter System for W7-X and IOFFE Institute
St. Petersburg, the Culham Science Centre (UKAEA) and
CIEMAT in Madrid are collaborating in the field of CX-
Neutral Particle Analysis.
8 Heating
8.1 Project Microwave Heating for W7-X (PMW)
The Electron Cyclotron Resonance Heating (ECRH) system
for W7-X is being developed and built by FZ Karlsruhe
(FZK) as a joint project with IPP and IPF Stuttgart. The
“Project Microwave Heating for W7-X” (PMW) coordinates
all engineering and scientific activities in the collaborating
laboratories and in industry and is responsible for the entire
ECRH system for W7-X. ECRH is designed for a microwave
power of 10 MW in continuous wave (CW) operation
(30 min) at 140 GHz, which is resonant with the W7-X magnetic
field of 2.5 T. It will consist of ten Gyrotrons with
1 MW power each, a low loss quasi-optical transmission
line and a versatile in-vessel launching system. It was
shown recently, that the gyrotrons operate also at 103.6 GHz
with about half the output power, which would extend the
flexibility of the ECRH significantly. PMW is strongly
involved in advanced and ITER related R&D activities.
8.1.1 The W7-X Gyrotrons (FZK)
The TED-Gyrotrons SNo. 2 and 3 failed to meet the specified
output power in the acceptance tests and were sent back
to TED for inspection. Strong defects in the electron beam
tunnel between gun and cavity were identified, which were
believed to be the reason for the measured power limitation.
TED presented a failure analysis indicating a fabrication
problem during brazing of these parts. An improved procedure
for the manufacture was qualified and the critical parts
were replaced in both, the SNo. 2 and 3 Gyrotrons. The
SNo. 2 (repair) Gyrotron was delivered to FZK by end of
July, where an output power of 0.55 MW/30 min and
0.85 MW/3 min were achieved, respectively. Then a water
Wendelstein 7-X
55
leak opened at the cw dummy load in the test stand, which
prevented further long pulse testing. The gyrotron was
shipped to IPP, where the FAT will be continued in January.
As short-pulse testing is still possible in the FZK test stand,
the Gyrotron SNo. 3 (repair) was installed by fall of the year
and short pulse testing has started. The Gyrotron SNo. 4 was
also equipped with the improved beam tunnel and passed
the Factory Acceptance Test (FAT) at FZK successfully
(0.5 MW/30 min, 0.91 MW/3 min). The gyrotron was then
transferred to IPP-HGW for the site acceptance test (30 min),
where 0.83 MW were achieved for 8 min, as the tests had to
be stopped, because the rf-beam parameters showed some
deterioration after a cooling failure. The gyrotron was
shipped to TED for inspection. The W7-X gyrotrons are
optimized for single frequency operation at 140 GHz. As the
gyrotron diamond window has a resonant thickness of 4λ/2
at 140 GHz, it is, however, also transparent at 105 GHz corresponding
to 3λ/2. Two modes, the TE 21,6 (103.6 GHz) and
TE 22,6 (106.3 GHz) exist in the vicinity of the desired frequency.
Both modes could be exited by tuning the resonant
magnetic field and adjusting the operation parameters
(I beam =40 A and U acc =62 kV). We have focused on the
TE 21,6 -mode operation, because the output beam was almost
perfectly centered on the output window, whereas the beam
from the TE 22,6 -mode was located somewhat off centre. As
seen from figure 27 (above), a maximum output power of
about 0.52 MW was achieved without collector voltage
depression corresponding to an efficiency η=21 %, which is
slightly higher than the theoretical prediction of η =17 %.
The output power drops with increasing depression voltage
while the efficiency increases from 21 % to 27 %. The corresponding
collector loading at 0 and 8 kV depression voltage
is 1.9 and 1.7 MW, respectively, which is incompatible
with the collector-loading limit of 1.3 MW. Thus only operation
with reduced beam current around 34 A (about 400 kW)
can be handled safely by the collector. The rf-beam was
transmitted through 7 mirrors of the quasi-optical transmission
line into a calorimetric cw-load. Transmission losses
of about 20 kW were measured, which compares well with
the transmission loss fraction at 0.9 MW, 140 GHz operation.
It is worth noting, that both the beam matching mirrors
as well as the set of polarizers can be used without modification.
The larger beam size at the lower frequency is expected
to introduce slightly higher losses as compared to
the nominal frequency. On the other hand the atmospheric
absorption is somewhat lower.
Assuming, that all series gyrotrons behave similar to the
Prototype, ECRH for W7-X will be operated as a two-frequency
system. As sketched in figure 27 the operation range
of experiments can then be extended towards different resonant
magnetic field of 1.86 T (X2 and O2 mode) and 1.25 T
(X3 mode), respectively. Once plasma start-up could be
achieved with X3-mode, which is not clear yet, operation at

1.25 T is of particular interest, because ECRH could then
provide a target plasma for NBI for high-ß physics studies,
which is most promising at low magnetic field.
800
600
400
200
TED-Prototype
RF-Power vs. Collector depression (103.8 GHz)
0
-4,0 0,0 4,0 8,0 12,0 16,0 20,0
Body-Voltage (kV)
3
2,5
2
1,5
1
0,5
0
I beam=40 A
104 GHz
140 GHz
X3
I beam=40 A
I beam=32-34 A
Accel.Voltage: 61.6 - 62.0 kV
Beam Current: 32 -40 A
Figure 27: Above: Output power in the TE 21,6 mode (103.6 GHz) as a
function of the depression voltage at constant acceleration voltage
(UACC=62 KV). Below: Cut-off density vs. resonant magnetic field for
different modes at both frequencies.
8.1.2 High-voltage system for Gyrotron power control and
protection (IPF)
The HV-control system for the W7-X Gyrotrons consists of
a high-voltage modulator unit, which provides and controls
the Gyrotron body voltage, and a crowbar unit with thyratronswitch
and integrated heater supply for the Gyrotron cathode.
The modulator is capable of delivering modulated body
voltages up to 30 kV at a rise time of up to 600 V/ms. The
HV system is remote controlled via optical fiber links by a
special control unit in the master control centre. The fabrication
of all units by IPF Stuttgart was finished and the installation
at IPP-Greifswald was completed in 2007 by adding
the three remaining modules. Nine out of the ten modules
passed the acceptance test, the SAT of the last module is
scheduled for beginning of 2008. The integration of the
X3
0 0,5 1 1,5 2 2,5 3
Magnetic field [T]
O2
X2
O2
X2
Wendelstein 7-X
56
many subsystems into the central control system is being
performed by experts from IPF and IPP, the final “as built”
technical documentation is in progress.
Figure 28: One of the two ECRH-towers. The heavy granite structure
serves as microwave absorber and has the favourable features of an optical
bench.
8.1.3 Transmission System (IPF)
The transmission line consists of single-beam waveguide
(SBWG) and multi-beam waveguide (MBWG) elements.
For each gyrotron, a beam conditioning assembly of five
single-beam mirrors is used. Two of these mirrors match the
gyrotron output to a Gaussian beam with the correct beam
parameters, two others are used to set the appropriate polarization
for optimum absorption of the radiation in the plasma.
A fifth mirror directs the beam to a plane mirror array, the
beam combining optics, which is situated at the input plane
of a multi-beam wave guide (MBWG). The MBWG is designed
to transmit up to seven beams (five 140 GHz beams,
one 70 GHz beam plus one spare channel) from the gyrotron
area (entrance plane) to the stellarator hall (output plane). A
mirror array separates the beams again at the output plane

and distributes them via CVD-diamond vacuum barrier windows
to individually movable antennas (launchers) in the
W7-X torus. Two symmetrically arranged MBWGs are used
to transmit the power of all gyrotrons. In 2007, a major work
package was the design completion and manufacturing of
the transmission system near the torus. This comprises the
reflectors type M13 and M14, which will be installed in two
“towers” in front of the W7-X ports.
The fabrication of both towers was finished, and the installation
of control systems for reflectors and launchers, support
structures, and granite absorbing plates has started.
Both towers, one of them is seen in figure 28, have to be
stored until W7-X assembly is completed and access is provided
for the installation at their final position in the torus
hall. In the meantime, retro-reflectors were mounted in the
beam-duct in the image plane at half distance of the MBWG
transmission line. Full distance transmission can be simulated
and tested by this arrangement. First calorimetric high
power measurements of the two-pass transmission efficiency
of the first part of the MBWG were performed, yielding a
loss of about 3 % for 10 reflections on the 2×3 MBWG-mirrors
and the 4 additional guiding mirrors, which is in good
agreement with calculations and low power measurements.
This result confirmes the high quality of the quasi-optical
concept for high power, long distance and low loss microwave
transmission.
8.1.4 In-vessel-components (IPP)
The design of the front steering ECRH-antennas in the Aand
E-type ports is compatible with full power cw requirements
and was finished in 2007. The CAD-drawing is
shown in figure 29. Most of the antenna components are
already manufactured, the assembly has started.
Figure 29: ECRH front steering antenna with bi-axially and individually
movable front mirrors
For the two optional high-field side launchers to be installed
in the narrow N-ports, it was decided to adopt the
remote steering scheme, which is based on the imaging
Wendelstein 7-X
57
properties of a square corrugated waveguide. A movable
reflector at the waveguide entrance controls the direction of
the beam injected into the waveguide; at the exit of the
waveguide near to the plasma edge, the beam is launched at
the same angle. For the N-ports, a solution with a bent
waveguide was chosen. This eases the integration of the
waveguides and leads to a lower antenna beam divergence
due to increased waveguide cross-section, but requires
thorough optimization of the position of the mitre bend and
the vacuum valve in the waveguide. The conceptual design,
as well as first optimization calculations have been started.
The ECRH operation range can be strongly extended if
heating scenarios with the second harmonic ordinary mode
(O2) and the third harmonic extraordinary mode (X3) can
be applied. The first enables high plasma density, which is
necessary for efficient divertor operation, the second allows
operation at a lower magnetic field. An incomplete single
pass absorption in the range of 40 % to 80 % has to be
accepted for W7-X parameters. Specially shaped reflectors
made from TZM (titanium, zirconium, molybdenum alloy)
will be installed to avoid the thermal overload of the high
field side heat shield by the microwave shine-through.
After first preliminary high power test in 2006 the reflectortile
was redesigned and its surface was polished to reduce
losses. The watercooled reflector tile was retested in the
ECRH-installation at Greifswald with about 0.5 MW incident
power, which is the expected “worst case” loading for
W7-X. The calorimetrically measured absorption reached
values of 0.3 %, which is consistent with the theoretical
value deduced from the material properties and with previous
low power tests. The surface temperature reaches
470 °C and 390 °C are measured at the cooling plate,
respectively, after 200 s for the worst case, which is acceptable.
The knowledge of the beam position and power load
at the reflector tiles is essential for reliable X3- and O2operation.
An array of small pick-up holes will therefore be
integrated into the tiles to measure the exact beam position
and the single pass absorption. The microwave signal is
transferred by 4 mm copper waveguides towards the B-type
port in the W7-X vacuum vessel. The positions of the
120 pick-up horns and the routing of the related waveguides
were defined in close cooperation with the W7-X
KIP group.
8.1.5 Advanced components and ITER-related R&D
8.1.5.1 Improved e-beam power dissipation at the Gyrotron
collector
The peak power load of the electron beam at the gyrotron
collector is a limiting factor for the next generation cw high
power gyrotrons with 1.5-2 MW output power. The W7-X
Gyrotrons are equipped with a conventional vertical sweep
coil system, which moves the electron beam intersection with
the collector surface up and down in the vertical direction.

This method generates strong power peaking at the turning
points as seen from figure 30 (c), which limits the overall
performance. An almost uniform power deposition is
obtained by adding a rotating transverse field sweeping system
(TFSS, 6 coils, 3 phase power supply, 50 Hz, constant
amplitude). A principle sketch is seen from figure 30 (a).
Figure 30: Principal sketch of the combined (a) Vertical Field (VFSS) and
Transverse Field Sweeping Systems (a) and an amplitude modulated VFSS (b).
(c): Power distribution along the gyrotron collector in vertical (z-) direction
under optimized conditions (red) and with vertical sweep only (black).
The collector surface is now efficiently used and the total
dissipated power can be nearly doubled as shown in figure
30 (c). The combination of both coil systems and the related
power supplies is, however, more complicated and expensive.
A more simple system using TFSS only with a slow amplitude
modulation (6 Hz) superimposed on the 50 Hz beam
rotation as sketched in figure 30 (b) is under investigation.
8.1.5.2 Fast Directional Switch of high power wave beams
The IPP Greifswald, IAP Nizhny Novgorod, IPF Stuttgart,
FZ-Karlsruhe, and IFP Milano have established a “Virtual
Institute” of the “Helmholtz Gemeinschaft deutscher Forschungszentren”
with the aim to develop a fast directional
switch (FADIS) for high-power microwave beams. FADIS
is a novel concept and will allow switching and/or combining
high power microwave beams on a fast timescale
(

4
3
2
1
0
intensity [a.u.]
-0.8 -0.6 -0.4 -0.2 0.0
time [ms]
8.1.6 Staff
Staff at IPP (W7-X-P and ZTE): B. Berndt, H. Braune,
V. Erckmann, F. Hollmann, L. Jonitz, H. P. Laqua, G. Michel,
F. Noke, F. Purps, T. Schulz, P. Uhren, M. Weißgerber.
Staff at FZK (IHM): A. Arnold, G. Dammertz, J. Flamm,
G. Gantenbein, R. Heidinger (IMF I), M. Huber, H. Hunger
(PMW), S. Illy, J. Jin, S. Kern, R. Lang, W. Leonhardt,
D. Mellein, B. Piosczyk, O. Prinz, T. Rzesnicki, U. Saller,
M. Schmid, W. Spiess, M. Stoner, J. Szczesny, M. Thumm,
J. Weggen, C. Zöller.
Staff at IPF Stuttgart: P. Brand, C. Lechte, M. Grünert,
W. Kasparek, M. Krämer, H. Kumric, O. Mangold, F. Müller,
R. Munk, B. Plaum, S. Prets, P. Salzmann, K.-H. Schlüter,
U. Stroth, D. Wimmer.
Scientific and Technical Staff
W7-X Subdivisions:
Project Coordination
H.-S. Bosch, A. Berg, H.-J. Bramow, J. Dedic, W. Fay,
J.-H. Feist, G. Gliege, M. Gottschewsky, D. Grünberg, K.-H.
Hanausch, D. Haus, U. Kamionka, T. Kluck, B. Kursinski,
A. Lorenz, D. Naujoks, R.-C. Schmidt, M. Schröder,
R. Vilbrandt.
Engineering
F. Schauer, T. Andreeva, V. Bykov, P. Chen, W. Chen,
P. Czarkowski*, W. Dänner*, A. Dübner, A. Dudek, K. Egorov,
J. Fellinger, D. Hathiramani, N. Jaksic, J. Kallmeyer,
J. Kißlinger*, M. Köppen, J. Lingertat*, M. Nitz, F. Scherwenke,
M. Sochor, L. Sonnerup*, A. Tereshchenko, S. Weber,
D. Zacharias, M. Ye.
Wendelstein 7-X
Power
Res
Nonres
Figure 32: Time traces of power signals. green: Gyrotron power. red: power
in resonant path. blue: power in non-resonant path. The gyrotron power
modulation results from the modulation of the acceleration voltage.
59
Design and Configuration
D. Hartmann, G. Adam, M. Banduch, Ch. Baylard*,
D. Beiersdorf, A. Bergmann, P. Biedunkiewicz, R. Binder,
R. Blumenthal, R. Brakel, T. Broszat, P. v. Eeten, N. Fuchs,
H. Greve, N. Hajnal, K. Henkelmann, F. Herold, A. Holtz,
C. Klug, J. Knauer, U. Krybus, L. Mollwo, A. Müller, K. Müller,
A. Okkenga-Wolf, D. Pilopp, T. Rajna*, N. Rüter, P. Scholz,
K.-U. Seidler, B. Sitkowski, F. Starke, M. Steffen, A. Vetterlein,
A. Vorköper, J. Wendorf, U. Wenzel, K. Zimmermann.
Magnets and Cryostat
U. Nielsen*, J. Baldzuhn, M. Bednarek, M. Bensouda-Korachi,
A. Cardella*, D. Chauvin*, G. Croari*,G. Ehrke, A. Friedrich,
D. Gustke, E. Hahnke, A. Hansen, B. Hein, D. Hermann,
K. Hertel, A. Hölting, H. Hübner, H. Jenzsch, P. Junghanns*,
T. Koppe, R. Krause, B. Missal, St. Mohr, A. Opitz, B. Petersen-
Zarling, J. Reich, K. Riße, P.G. Sanchez*, M. Schrader,
R. Schröder, D. Theuerkauf, S. Thiel, V. Tomarchio*, H. Viebke,
S. Wendorf*.
Supply Systems and Divertor
M. Wanner, H. Bau, D. Birus, A. Braatz, C. Dhard,
F. Füllenbach, L. Guerrini*, M. Ihrke, T. Mönnich, M. Nagel,
M. Pietsch, Th. Rummel, M. Schneider.
Assembly
L. Wegener, J. Ahmels, A. Benndorf, T. Bräuer, M. Czerwinski,
A. Domscheidt, H. Dutz, M. Endler, S. Gojdka, H. Grote,
H. Grunwald, A. Hübschmann, F. Hurd*, D. Jassmann,
A. John, S. Jung, A. Junge, R. Krampitz, F. Kunkel, H. Lentz,
E. Müller, H. Modrow, J. Müller, U. Neumann, D. Rademann,
H. Rapp*, L. Reinke, K. Rummel, D. Schinkel, W. Schneider,
U. Schultz, E. Schwarzkopf, Ch. von Sehren, O. Volzke,
K.-D. Wiegand.
Physics
F. Wagner, R. Wolf, T. Bluhm, H. Braune, R. Burhenn,
J. Cantarini*, A. Dinklage, V. Erckmann, P. Grigull,
H.-J. Hartfuss, C. Hennig, U. Herbst, D. Hildebrandt,
M. Hirsch, L. Jonitz, R. König, P. Kornejev, M. Krychowiak,
G. Kühner, A. Kus, H. Laqua, H. Laqua, M. Laux, M. Lewerentz,
G. Michel, I. Müller, U. Neuner, F. Noke, E. Pasch, S. Pingel,
R. Preuß*, F. Purps, T. Richert, J. Schacht, W. Schneider,
A. Schütz, A. Spring, H. Thomsen, P. Uhren, S. Valet, A. Weller,
A. Werner, M. Ye, D. Zhang.
Technical Services (TD)
R. Krampitz, M. Haas, M. Müller, J. Sachtleben, M. Winkler.
IPP Garching
Experimental Plasma Physics I (E1): N. Berger, B. Kurzan,
B. Mendelevitch, C. Li, H. Murmann, A. Peacock, B. Petzold,

M. Rott, S. Schweizer, R. Stadler, B. Streibl, R. Tivey,
T. Vierle, S. Vorbrugg, G. Zangl.
Materials Research (MF): M. Balden, H. Bolt, J. Boscary,
H. Greuner, F. Koch, S. Lindig, G. Matern, M. Smirnow,
R. Brüderl, B. Böswirth, J. Kißlinger, K. Bald-Soliman.
Technology (TE): W. Becker, B. Eckert, H. Faugel, F. Fischer,
B. Heinemann, D. Holtum, M. Kammerloher, M. Kick,
C. Martens, P. McNeely, J.M. Noterdaeme, S. Obermayer,
R. Pollner, R. Riedl, N. Rust, G. Siegl, W. Sinz, E. Speth,
A. Stäbler, P. Turba.
Computer Center Garching (RZG): P. Heimann, J. Maier,
M. Zilker.
Central Technical Services (ZTE) Garching: B. Brucker,
H. Eixenberger, R. Holzthüm, M. Huart, N. Jaksic, M. Kluger,
J. Maier, K. Pfefferle, H. Pirsch, J. Simon-Weidner, H. Tittes,
M. Weissgerber, F. Zeus.
Cooperating Research Institutions
Forschungszentrum Jülich (FZJ), Germany: W. Behr,
G. Bertschinger, W. Biel, A. Charl, J. Collienne, G. Czymek,
A. Freund, B. Giesen, D. Harting, H. Jägers, H. T. Lambertz,
M. Lennartz, Ph. Mertens, O. Neubauer, O. Ogorotnikova,
A. Panin, M. Pap, A. Pospieszczyk, U. Reisgen, D. Reiter,
J. Remmel, M. Sauer, W. Schalt, L. Scheibl, H. Schmitz,
G. Schröder, J. Schruff, B. Schweer, W. Sergienko, R. Sievering,
R. Uhlemann, J. Wolters.
Forschungszentrum Karlsruhe (FZK), Germany: A. Arnold,
G. Dammertz, J. Flamm, W. Fietz, G. Gantenbein, R. Heidinger,
R. Heller, M. Huber, H. Hunger, S. Illy, J. Jin, S. Kern, R. Lang,
W. Leonhardt, D. Mellein, K. Petry, B. Piosczyk, O. Prinz,
T. Rzesnicki, U. Saller, M. Schmid, W. Spiess, M. Stoner,
J. Szczesny, M. Thumm, J. Weggen, C. Zöller.
Stuttgart University (IPF), Germany: P. Brand, M. Grünert,
W. Kasparek, M. Krämer, H. Kumric, C. Lechte, O. Mangold,
F. Müller, R. Munk, B. Plaum, S. Prets, P. Salzmann, K.-
H. Schlüter, U. Stroth, D. Wimmer.
Ernst-Moritz-Arndt-Universität Greifswald, Germany:
B. Pompe.
Universität Rostock, Germany: A. Holst.
Universität Stuttgart, Institut für Kunststoffprüfung und
Kunststoffkunde, Germany: G. Busse.
IPHT – Institut für Physikalische Hochtechnologie e.V.,
Jena, Germany: W. Ecke, K. Fischer, V. Schultze.
PTB Pysikalische Technische Bundesanstalt Braunschweig,
Germany: H. Schumacher, B. Wiegel.
UKAEA, Culham, UK: B. Brade, M. Tournianski.
Commissariat á L’Energie Atomique (CEA), Saclay,
France: A. Daël, L. Genini, T. Schild.
CRIL Group, Aloytech, France: D. Galindo, G. Vitupier.
CIEMAT, Madrid, Spain: R. Balbin, E. Ascasibar, L. Esteban,
T. Estrada, C. Hidalgo, M. Sanchez, V. Tribaldos.
IST/CFN, Lisbon, Portugal: P. Carvalho.
LT Calcoli, Italy: F. Lucca.
Wendelstein 7-X
60
ENEA Centro Ricerche Energia, Frascati, Italy:
A. Capriccioli, G. Mazzone, L. Semiraro.
CNR Istituto di Fisica del Plasma, Milano, Italy: M. Romé.
CRPP Ecole Polytechnique Federale de Lausanne,
Switzerland: K. Appert, D. Eremin.
Technical University Graz, Austria: W. Kernbichler.
University of Opole, Poland: I. Ksiazek, F. Musielok.
Technical University Szczecin, Poland: P. Berszynski, I. Kruk.
Maritime University of Szczecin (Akademia Morska),
Poland: B. Bieg, Y. Kravtsov.
IPPLM Institute of Plasma Physics and Laser Microfusion
Warsaw, Poland: Galkowski, L. Ryc, M. Scholz,
Zzydlowski.
The Henryk Niewodniczanski Instiute of Nuclear
Physics, Kraków (IFJ PAN), Poland: M. Jezabek, Z. Zulek,
M. Stodulski.
Wroclaw Technical University and Wroclaw Technology
Park (WTU WTP), Wroclaw, Poland: M. Chorowski.
Soltan Institute for Nuclear Studies (IPJ), Otwock-Swierk,
Poland: G. Wrochna.
University of Ljubljana, Faculty of Mechanical Engineering,
Ljubljana, Slovenia: J. Duhovnik, T. Kolsek.
Budker Institute of Nuclear Physics, Novosibirsk; Russia:
V. I. Davydenko, A. Ivanov, I. V. Shikhovtsev.
Efremov Institute, St. Petersburg, Russia: A. Alekseev,
A. Malkov.
A.F. Ioffe Physico-Technical Institute of the Russian
Academy of Sciences, Russia: S. Petrov, A. Kislyakov.
Technical University, St. Petersburg, Russia: S. J. Sergeev.
Kurchatov Institute, Moscow, Russia: M. Iasev.
Institute of Applied Physics (IAP), Nizhnynovgorod, Russia:
A. Shalashov.
Institute for Nuclear Research, Kiev, Ukraine: Y. I. Kolesnichenko,
V. V. Lutsenko, Y. V. Yakovenko.
Kharkov Institute of Physics and Technology, Ukraine:
L. Krupnik, A. Melnikov, D. Perfilov.
Research Institute for Particle and Nuclear Physics,
Budapest, Hungary: S. Zoletnik, G. Kocsis, A. Molnár,
S. Récsei, J., Sárközi, A. Szappanos.
Princeton Plasma Physics Laboratory (PPPL), USA:
S. Hudson, A. Reiman, M. Zarnstorff.
Oak Ridge National Laboratory (ORNL), USA: J. H. Harris,
D. A. Spong.
University of Wisconsin, Madison, USA: J. Talmadge.
Kyoto University, Japan: S. Murakami, F. Sano.
National Institute for Fusion Science (NIFS), Toki, Japan:
T. Funaba, S. Okamura, Y. Suzuki, K. Toi, K. Y. Watanabe,
H. Yamada, M. Yokoyama.

WEGA
Head: Dr. Matthias Otte
Laboratory Plasma Devices WEGA and VINETA
Electron Cyclotron Wave Physics
The plasma at WEGA is generated
for low magnetic field operation
of B 0 =60 mT by magnetrons
at a frequency of 2.45 GHz.
The over-dense plasma operation
(>10 times cut-off density for
2.45 GHz) is achieved with mode
conversion Bernstein wave heating.
Raytracing calculations by Preinhalter and Urban, (IPP
Prague/Czech Republic) confirmed the propagation of the
Bernstein waves in the over-dense plasma region. Although the
WEGA double slot antenna has a symmetric emission profile in
toroidal co- and counter direction, these calculations also showed
a beam propagation in one toroidal direction only, which should
generate Bernstein wave driven toroidal currents. The predicted
current was detected by an external out-of-vessel Rogowski
coil and by the primary coil current at the WEGA transformer.
Power modulation experiments (6 kW on-off at a modulation
frequency of 30 Hz) showed a maximum toroidal current amplitude
of I t =50 A. This current strongly depends on the magnetic
configuration and could even be reversed in case of magnetic
shear reversal. Furthermore, the current density profile inside the
plasma could be measured with small movable Rogowski coils.
This makes WEGA an unique experiment to investigate
Bernstein wave driven currents. The 28 GHz ECRH system was
successfully built and commissioned and is now fully operational
at the second harmonic resonance at 0.5 T. A microwave power
of up to 10 kW is typically used for 15 s plasma operation. The
waveguide system generates an HE11 beam, which is focussed
into the plasma center by an optimized double mirror system inside
the plasma vessel. The resonant character of the absorption
could be verified by on- and off-axis heating experiments.
In argon plasmas a density of n e =4.9×10 18 m -3 and a temperature
of T e =25 eV in the central region could be achieved. Furthermore,
the microwave stray radiation measurement indicates a
strongly enhanced resonant absorption by multiple wall reflections
as predicted by TRAVIS ray-tracing code calculations.
However, in hydrogen discharges an electron temperature
T e >20 eV is achieved already at the plasma edge. For such plasmas
the central region is not longer accessible with simple
Langmuir probes because they start to emit electrons distorting
the characteristics. Therefore, contact-less diagnostics, like Heavy
Ion Beam Probe (HIBP), Electron Cyclotron Emission (ECE),
a bolometer and a reflectometer are being implemented now.
Results from Plasma Experiments
Turbulence studies have been continued in order to identify the
driving instability mechanism and to give a three-dimensional
characterization of the structure of the turbulence. A small
On WEGA experiments were focused on electron
cyclotron wave physics, on fluctuation,
biasing studies and preparations for 0.5 T plasma
operation. Furthermore, the prototype installation
of the W7-X control system made significant
progress. In VINETA it has been achieved to
control drift wave turbulence by influencing nonlinearly
the intrinsic parallel drift wave currents.
The investigations of non-linear wave phenomena
was extended to whistler wave solitons.
61
cross-phase between density and
potential fluctuations is a strong
indicator for drift waves. Additional
hints for drift wave turbulence
could be found, namely
a propagation of turbulent structures
in electron diamagnetic
drift direction after subtraction of
E×B convection and a finite
average parallel wavenumber in
the order of k || ≈10 -2 k θ . The precise
knowledge of the magnetic
field topology allows insight into the parallel dynamics of turbulence.
Turbulent structures in WEGA have a three-dimensional
character and arise preferably on the low field side of the
torus. Furthermore, the influence of magnetic islands on turbulence
was studied. WEGA offers the unique possibility to control
islands and to study turbulence in this region with high
spatial and temporal resolution. Initial experiments showed a
locally enhanced fluctuation amplitude and turbulent transport
in the presence of magnetic islands. Biasing experiments
using carbon probes fitting the shape of the last close flux surface
(LCFS) demonstrated in argon plasmas that a positive
biasing just inside the LCFS increases the poloidal rotation by
a factor of 2 in the maximum. With probe voltages exceeding
+70 V a high temperature regime has been reached with temperatures
of up to T e =25 eV in the vicinity of the LCFS.
Diagnostic Development
The HIBP is a first contactless diagnostic designed for 28 GHz
ECR heated plasmas operation. The ion source was modified
to increase the beam current stability. With an optimised ion
source first profiles of the plasma potential and the total current
were measured. The profiles are in good agreement with
Langmuir probe data. In collaboration with the HIBP group at
TJ-II (Madrid/Spain) and HIBP in KIPT (Kharkov/Ukraine)
modifications of data acquisition and control systems have
been performed in order to decrease the noise level of the
obtained signals. Furthermore, the design of a multi-channel
ECE-system started which will provide information on the
temperature profile of the electrons for 0.5 T operation.
Prototype of W7-X Control System
The setup of a prototype installation of the W7-X control
system is in progress. The central control system, power
supplies, cooling system could be successfully tested in
autonomous operation. An integrated test of all components
is anticipated for the beginning of 2008.
Scientific Staff
D. Andruczyk, O. Lischtschenko, S. Marsen, Y. Podoba,
M. Schubert, T. Stange, G. B. Warr, F. Wagner.

VINETA
Head: Prof. Dr. Olaf Grulke
Device and Operational Parameters
VINETA is a long, cylindrical helicon plasma device, specifically
tailored to study plasma waves and instabilities. The nonresonant
rf helicon wave heating provides high plasma densities
at relatively low electron temperatures (n=1019 m-3 , T ≈3eV e
for a rf frequency f =13.56 MHz, rf power of P =5 kW, and
rf rf
magnetic field B=0.1 T). The main diagnostic tools are electrostatic
and magnetic probes. In addition to standard Langmuir
probe diagnostics advanced active induction probes have
been developed to achieve reasonable signal to noise ratios
at the low frequencies of drift wave and Alfvén wave existence
(f=50 kHz). In the high frequency range induction
probes with high capacitive pickup rejection are used for the
measurements of the magnetic wave field of whistler waves.
Nonlinear Interaction of Drift Waves and Driven Parallel Currents
A key feature of the dynamics of drift wave modes and turbulence
is the parallel electron response associated with the
drift wave instability. Using highly sensitive magnetic probes
the parallel current structure of single saturated drift wave
modes has been measured. Figure 1 shows plasma density
fluctuation pattern and the associated perpendicular magnetic
field fluctuations of a m=3 drift wave mode for two phases of
the drift mode in half of the azimuthal cross section. The magnetic
field fluctuations show the signature of parallel current
filaments, which are correlated with the drift mode pressure
perturbations. To directly influence of the parallel drift wave
currents two approaches are persued: First, a shear Alfvén
wave is excited with a frequency close to the drift wave frequency.
The parallel currents of the drift wave and the Alfvén
wave interact nonlinearly, which is observed as frequency
pulling of the drift mode by the Alfvén wave. Second, a more
y [mm]
80
60
40
20
0
-20
-40
-60
-80
-80 -60 -40 -20 0 -80 -60 -40 -20 0
x [mm] x [mm]
Laboratory Plasma Devices WEGA and VINETA
0.3
0.2
0.1
0
-0.1
-0.2
-0.3
Figure 1: Pressure fluctuations (color coded) and associated perpendicular
magnetic field fluctuations (arrows) for a single m=3 drift mode in the
azimuthal plane perpendicular to the ambient magnetic field.
density fluctuations [a.u.]
62
advanced scheme is to drive mode selective parallel currents
either inductively by a set of eight azimuthally arranged magnetic
saddle coils or with electric contactors in the plasma.
With this mode selective current drive we achieved a full
suppression of the drift wave turbulence. Figure 2 shows an
example of a typical power spectral density for drift wave
turbulence as observed in VINETA and the result of the mode
selective current drive with mode number m=2. In the turbulent
state without current drive the spectrum is broad and displays
a power law decrease for frequencies f≥10 kHz. The
spatiotemporal measurement shows incoherent fluctuations
without any distinct mode number. When parallel currents are
driven, drift wave turbulence is fully suppressed and the fluctuation
energy is transferred into a coherent m=2 drift mode.
S [dB] S [dB]
40
0
-40
-80
40
0
-40
-80
0 10
f [kHz]
20
Whistler Waves
In previous measurements we observed a systematic deviation
of the whistler wave behaviour from the linear dispersion
relation at a frequency of roughly half the electron cyclotron
frequency. At this frequency the whistler wave phase velocity
equals its group velocity and it has been suggested that whistler
wave solitons, so-called oscillitons, might be responsible for the
observed deviations. Dedicated measurements of those deviations
and the associated damping of whistler waves in VINETA
revealed first evidence for the existence of whistler solitons. The
unambiguous identification of oscillitons by wave package dispersion
measurements will be the subject of further investigations.
Scientific Staff
Φ [π] Φ [π]
0
2
C. Brandt, O. Grulke, T. Klinger, J. Pfannmöller, K. Rahbarnia,
A. Stark, N. Sydorenko, S. Ullrich, T. Windisch.
2
1
1
0
0 0.5 1
time [ms]
1.5 2
Figure 2: Power spectral density of plasma density fluctuations and associated
spatiotemporal plot of density fluctuation time series along an
azimuthal circumference for the case of drift wave turbulence (top row) and
the controlled situation when a m=2 current pattern is driven
Part of the VINETA program is carried out under the auspices of the Transregional
Special Collaborative Research Center SFB-TR24 “Fundamentals
of Complex Plasmas”.
δ n [a.u.]
δ n [a.u.]

ITER

Introduction
A major new part of the IPP contribution
to ITER during 2007
was via participation in the
design review process. The
design review was divided into
eight working groups who were
charged with evaluating and prioritising
the list of open issues in
the ITER design and with finding proposed solutions to
these issues. IPP scientists participated in four of the eight
working groups: Design Requirements and Physics Objectives;
Buildings; Heating and Current Drive; and In-Vessel Components.
The IPP also contributes actively to the physics
definition of ITER via the International Tokamak Physics
Activity. IPP expertise is in demand for a wide range of activities
in support of ITER, based not only on ASDEX Upgrade
experience but also on know-how in the Technology,
Theory, Materials and Stellarator Divisions. This work varies
from studies of plasma scenarios to work on specific technical
systems and is carried out largely under contracts within
the European Fusion Development Agreement (EFDA).
Heating Systems
Development of RF Negative Ion Sources
In 2007, the IPP RF driven ion source was chosen by ITER as
the new reference source for the ITER neutral beam system.
The main advantages of the RF source are the in-principle
maintenance free operation and the expected much lower Cs
consumption due to the lack of evaporating parts in the source.
Some open issues, however, are still to be addressed: (1) the
simultaneous demonstration of ITER-relevant ion source
parameters for a pulse duration of up to one hour from a
PINI size extraction area; (2) the demonstration of a suffi-
Current / (A)
4
3
2
1
0
45 kW, 0.4 Pa, U ex = 6 kV, j ion = 120 A/m 2
0 10 20 30 40 50 60
Time / (min)
ITER Cooperation Project
Head: Dr. Lorne Horton
Electrons
The IPP contributes to the ITER Project in a wide
range of activities. Tasks range from R&D for
heating systems and diagnostics to development
of integrated plasma scenarios. In addition, the
IPP is playing a leading role in contributing to
the ITER physics definition and objectives via
contributions to the International Tokamak
Physics Activity and the ITER design review.
Ions
Figure 1: The first stable one hour pulse at MANITU. No feedback control
for electron suppression was necessary.
65
ciently homogeneous large RF
plasma operation with caesium
and negative ion densities in the
required range of a few 10 17 m -3 .
The long pulse test facility
MANITU was further upgraded
by installing a new plasma grid
and an actively cooled bias plate.
With the new setup, stable long
pulses are now possible (figure 1).
The parameters achieved so far are, however, below the ITER
requirements. The main problem for long pulses is still the
rising electron current within the first 100-200 seconds; the
ion current remains stable during the pulse.
The ion source test facility RADI, equipped with a source of
approximately the width and half the height of the ITER
source, aims to demonstrate the required plasma homogeneity
of a large RF source. Full size extraction is not possible.
First results of the homogeneity of a large RF driven deuterium
plasma in volume operation have been obtained.
The experiments at BATMAN concentrate now on basic
studies of negative ion formation and extraction as well as
on electron suppression, on the support of the design of the
ELISE and ITER source and on the further development of
diagnostics. Figure 2 shows as an example the measurement
of the electron energy distribution function (EEDF) using
the so-called Boyd-Twiddy method.
Figure 2: Spatial dependence of the electron energy distribution function of
the IPP RF source from the plasma grid (0 cm) to the driver exit (19 cm)
A new test facility ELISE (Extraction from a Large Ion
Source Experiment) is currently being designed for long pulse
and large-scale extraction from a half-size ITER source. ELISE
is an important step between the small-scale extraction experiments
at BATMAN and MANITU and the full size ITER
neutral beam system. Due to the limits of the IPP HV system,
only pulsed extraction is possible. The start of integrated
commissioning is planned for the end of 2009. ELISE
makes use to a large extent of existing hardware at IPP,

including the cryo system of MANITU and the CODAC
system of RADI. Hence both these test facilities are planned
to be decommissioned in the course of 2009.
IPP continued its contribution to the design of the International
Neutral Beam Injector Facility in Padua, Italy. The
main activity of IPP is the strong support of RFX Padua –
also by the exchange of personnel – in the design of the full
size RF source and the RF circuit. Smaller activities are the
support of the layout of the source and beam diagnostic system
and the design of an alternative magnetic ion removal system.
ICRF Antenna Design
Substantial progress has been made this year in the definition
of the ICRF antenna. At a meeting in Ringberg, hosted by
IPP, the groundwork was laid for the ITER Design Review
working group to recommend that future work would concentrate
on the “ex-vessel matching” option. A number of
tasks were defined by the ITER Design WG. IPP contributed
to one of those: the grounding of the antenna. As the antenna
plug is presently only grounded at the port plug flange, the
plug itself works as the inner conductor of a transmission
line. It can therefore sustain eigenmodes, which lead to high
voltages between the antenna plug and the surrounding blankets.
Proper grounding can avoid this.
Europe has also made progress in the legal aspects of setting up
a consortium (CYCLE), which is meant to take the responsibility
for the ICRF antenna design. IPP is part of the consortium.
Optimisation of the Upper ECRH Launcher
For the optimization of the “front-steering” launcher, beam
shaping of the radiated antenna beams by waveguide mode
mixtures is under investigation. Converters from smooth circular
waveguide modes to Gaussian beams have been designed.
To enlarge the database on cooling requirements of launcher
mirrors, Ohmic losses of mirror samples that had been
exposed to fusion plasmas were measured with a 3-mirror
resonator at 170 GHz. After one year of operation, launcher reflectors
from ECRH systems of ASDEX Upgrade and W7-AS
showed visible coatings on the surface. As a result, the
Ohmic loss increased by a factor of 1.4 to 1.9 with respect to
an identical new sample. Compared to theoretical values,
the Ohmic loss was higher by factors between 2.3 and 3.0.
ECRH Reliability Data
As part of an EFDA task, the operational experience of the
ASDEX Upgrade ECRH-1 system has been documented with
respect to reliability and main reasons for failures. For this purpose
the old logbooks have been revisited for all pulses between
7.5.1998 and 25.4.2006 in which ECRH was requested (1806
pulses) and a condensed database has been delivered to EFDA.
This information will be recorded in the “Fusion Component
Failure Rate Database” and used as one of the inputs for
making projections of the reliability of the ITER ECRH system.
ITER Cooperation Project
66
Physics Integration
ECRH Physics Integration
Work on the design of the ITER ECRH Upper Launcher was
continued together with partners at CRPP, CNR, FOM and
FZK. An optimization of the mirror design of the reference,
front steering option was analyzed with the aim to minimize
spread in individual beams reflected off one mirror. In the
physics area, work was started on deriving a criterion for FIR
NTM triggering. This criterion will be of the same type as
that for sawtooth stabilisation (i.e. figure of merit I ECCD /d 2 ),
but numerical values can only derived from code modelling
which is in progress. Arrangements have been started amongst
the EU partners to form a consortium that can bid for the
ITER procurement package for the Upper Launcher.
Erosion/Redeposition Studies in PSI-2
In close cooperation with the EFDA group in Garching,
experiments were performed at the PSI-2 plasma generator
in Berlin aiming to test whether nitrogen is suited to serve as
a scavenger gas. Methane was blown into hydrogen discharges
with nitrogen injected into the target chamber.
Deposition or erosion of hydrocarbon layers was monitored
in situ. The various molecules and radicals being produced
in the plasma could be identified using mass spectrometry.
A strong effect was observed in the case of nitrogen injection,
whereas no effect was found for other gases. The variations of
the layer thicknesses were measured on collectors located
either in the target chamber or in the pumping duct. In the target
chamber the growth rate was reduced considerably (0.89
to 0.09 nm/min) while N 2 was blown into the discharge. In the
pumping duct even a reversion from growth (+0.05 nm/min)
to erosion (-0.044 nm/min) could be achieved.
Non-axisymmetric Stability & Resistive Wall Modes
The 3D code package consisting of the CAS3D, STAR-
WALL and OPTIM codes has been applied to stability and
feedback studies of ITER scenario 4. From these studies, it
has been determined that: the no-wall beta limit is β N ~2.3;
the ideal wall limit is β N ~3.55 with a closed wall and ~3.14
for a wall with holes; and no feedback stabilization could be
achieved with β N =2.676. These results suggest that the considered
equilibria and feedback coil system may be inappropriate
for stabilizing the RWM. Nevertheless, before a final
conclusion is drawn, further benchmark calculations with
the MARS, KINX and VALEN codes are required and
remaining differences between codes have to be clarified.
Retention in Mixed Materials
In the framework of an EFDA Task, a study was made of the
retention of fuel ions in mixed materials such as will be
present in ITER. This work is reported in the Plasma-Facing
Materials Chapter of this annual report.

3D Analysis of Impurity Transport and Radiation for ITER Limiter
Start-up Configurations
Three-dimensional modelling of ITER SOL transport during
the start-up limiter phase with the EMC3-EIRENE code has
been extended to include the limiter-released Be production,
transport and radiation. The distributions of the single Be
charge-state densities and line radiation have been simulated
for two plasma densities =0.2 n G , 0.5 n G and three plasma
configurations, I p =2.5, 4.5, 6.5 MA. All Be charge states
exhibit a strong poloidal density modulation due to the small
poloidal extension of the limiters.
Diagnostics
ITER Procurement Package 21
In January 2007 a consortium of the Euratom Fusion
Associations (IPP, HAS, FZK, CEA and CIEMAT) under
the leadership of IPP began work on the task of providing a
project plan for the full development of ITER Procurement
Package 21 (PP21). PP21 consists mainly of the bolometer
diagnostic and the pressure-gauge diagnostic, but also of all
diagnostic hardware associated with lower port 16, including
that of other “client” diagnostics.
The project plan contains a definition of the scope of PP21,
of the work breakdown structure (WBS), the WBS dictionary,
an implementation schedule and management plans for
risk, procurement, communication, costs and quality. The
project plan developed by IPP concentrates on the needs of
the bolometer diagnostic and the port engineering activities.
Aspects of the project plan concerning the pressure gauge
diagnostic are the responsibility of CIEMAT.
HAS contributes with the performance analysis of the system
and the finite element analysis of the thermal behaviour of
bolometer mini-cameras. FZK has made its experience in the
nuclear analysis of the ITER environment available for the
analysis of nuclear heat loads on models of mini-cameras.
CEA contributed with its experience on various bolometer
detector concepts and on irradiation tests. In addition to providing
the project leader, IPP provided the lead engineer and
contributed with research activities on the metal-resistor
bolometer detector and to the integration of the diagnostic
into the ITER CODAC system. In order to develop the project
plan and to provide urgently needed data for the integration
of the diagnostic in ITER, a number of R&D and engineering
tasks had to be carried out in parallel to developing the project
plan. The ongoing research activities on the reference metalresistor
bolometer detector were continued and a prototype
with a 4 μm Pt absorber was successfully tested in ASDEX
Upgrade. Irradiation tests are in preparation as are the contracts
with a new cooperation partner for the development of
thin-foil detectors with 12 μm absorbers.
In April a proposal for the LOS distribution was submitted
to ITER. This was further refined in order to account for the
ITER Cooperation Project
67
changes following the ITER design review. Based on this distribution,
an initial performance analysis of the diagnostic was
made. A preliminary ITER bolometer mini-camera and collimator
were designed and adapted to all locations in the divertor
cassettes (an example for divertor cassette 45 is given in
figure 3) and to some in the VV, thus giving the basic definitions
of the interfaces for the integration of the bolometer diagnostic.
Figure 3: Distribution of mini-cameras as foreseen for the locations in
divertor cassette 45
The mini-camera/collimator model was analysed for its thermal
behaviour in the divertor and behind the inner heat shield
under conditions expected for the ITER standard scenario 2.
The results showed that the mini-cameras should be able to
cope with the demanding boundary conditions if sufficient
thermal contact to actively cooled structures can be provided.
In-Vessel Neutral Pressure Measurement
The ASDEX Pressure Gauge (APG) is, at present, the main
candidate for in-vessel neutral pressure measurement in
ITER. The response of conventional APGs is found to saturate
at around 15 Pa, below the ITER requirement of 20 Pa.
With small modifications to the gauge geometry and potential
settings, however, it is possible to obtain monotonic output
with sufficient slope up to the maximum achievable pressure
of 30 Pa at 6 T. The improved pressure range is achieved at
the expense of a lower sensitivity and a somewhat stronger
dependence on the magnetic field.
Test of a Compact Soft X-Ray Spectrometer
A prototype of a compact SXR spectrometer for ITER has
been designed at the Kurchatov Institute in Moscow and is
presently being tested in ASDEX Upgrade. At present, one
spectrometer channel is equipped with a crystal made of
high purity quartz and a deeply depleted back illuminated
CCD camera chip for radiation hardness. The spectrometer
is set to monitor the resonance line of He-like argon. Due to the
large diffraction angle used (≈70°), a high resolving power

of λ/Δλ≈6800 is reached despite the compact dimensions.
First results were obtained during the 2007 campaign allowing
the extraction of Ar concentrations and ion temperatures
in the central plasma with a temporal resolution of 8 ms.
Dust Measurement
The production of dust is an important safety issue for ITER.
Investigations in AUG have been started to compare different
dust measurement techniques and to quantify the dust produced
in a tungsten wall device. Methods under test include a filtered
vacuum collection technique, Si wafer collectors, an in-situ
monitor developed by PPPL and a fast visible camera with a
tangential view. First investigations show spheres of tungsten
with a typical diameter of 1 μm. With a frame rate of 20 kHz,
the fast camera can produced 8 GB of data during one discharge.
Up to now only manual data evaluation has been done.
Typical speeds of 100 m/s are observed for dust particles.
ITER Core Charge Exchange System
Simultaneous observations of charge exchange (CX) transitions
from Ar XVI, XVII and XVIII were obtained in AUG
H-mode plasmas to provide experimental validation of new
fundamental CX cross-sections for Ar. In addition, the influence
of W I and W II line intensities on ITER CX spectra
has been calculated. Using a simple model for W sources, it
is calculated that the CX-lines from C VI and N VII are
unperturbed while the Be IV and He II spectrum has to deal
with only two W I lines. The Ne X and Ar XVIII CX-lines
suffer from several W I lines and therefore may not be suitable
for ion temperature measurements, unless the lines of
sight are chosen with great care.
ITER Design Review
Operating Scenarios for ITER (Current Rise and Current Decay)
In order to achieve the range of scenarios foreseen for ITER,
it is necessary to access a range of q-profiles at the start of the
burn phase. For the ITER Design Review, experimental data
from ASDEX Upgrade have been supplied for two cases.
The first case is based on a dataset of 84 Ohmic pulses with
q 95

Plasma-wall-interactions
and Materials

Surface Processes on Plasma-
Exposed Materials
Simultaneous Irradiation of
Tungsten with D and C at
Elevated Temperatures
Tungsten (W) erosion and carbon
(C) layer growth during simultaneous
irradiation by combined
D + -C2 3
Plasma-facing Materials and Components
Head: Prof. Dr. Dr. Harald Bolt, Dr. Joachim Roth
- ions at 400 °C has been
investigated using the mass-analyzed
dual-beam ion accelerator
at IPP. The simultaneous bombardment results in a competition
of erosion and implantation processes that cannot be
described by the linear superposition of the respective pure
species sputtering. Instead, one observes two regimes of
either continuous growth of a C layer or continuous W erosion.
W films deposited on nickel and graphite substrates resulting
in “smooth” and “rough” surfaces respectively, were used as
a model system for irradiation. The different substrates were
chosen to isolate the effect of surface roughness from chemical
erosion, since to this date, no experiments have conclusively
shown a clear correlation between C chemical erosion in the
W matrix, and its effect on W sputter yield and C levels in the
implantation zone. The incident ion energy of D + and C - was
3 keV and 6 keV respectively, and were chosen to obtain the
maximum flux. The dynamics of W sputtering was measured
in-situ by Rutherford Backscattering Spectrometry using
2.5 MeV 3 He ions. Corresponding concentrations of implanted
C and D were measured by Nuclear Reaction Analysis. The
incident C/D ratio was varied over the range 3-20 % and
was determined by a new diagnostic tool, the Beam Viewing
System (BVS), which was able to record in real time quantitative
images of the C and D beam intensities.
For a given C/D ratio at low fluences, the W sputter yield and
total C concentrations at 400 °C deviate little from RT measurements.
However at higher fluences, an increase in W sputtering
and C re-erosion is observed for 400 °C measurements,
resulting in a shift of the transition point from steady state W
erosion to C deposition to higher C/D ratios. Further experiments
at 500 and 600 °C are planned. Experimental results
will be used to benchmark the kinematic code TRIDYN coupled
with the module YCHEM, which provides the chemical
erosion rate of C.
Synergistic Erosion of Hydrocarbon Films Studied by Molecular
Dynamics
Hydrogen isotope retention in carbon-based plasma-facing
materials is a potentially limiting constraint in the long-term
operation of fusion reactors since tritium will be used as
fuel, and hence the tritium inventory build-up may lead to
various safety issues limiting the operation as well as to economic
constraints due to fuel retention.
Within the project “Plasma-facing Materials and
Components” the areas of plasma-wall interaction
studies, material modification under plasma
exposure, development of new plasma-facing
materials and their characterisation have been
merged to form a field of competence at IPP.
The work supports exploration and further development
of the fusion devices of IPP and also
generates basic expertise with regard to PFCrelated
questions in ITER and fusion reactors.
71
The plasma-facing components
interact with both energetic and
thermal hydrogen species. In
order to understand and quantify
the influence of the energetic particles
on carbon erosion, various
experiments employing hydrogen
ion beams have been performed.
The experiments showed
that the resulting erosion rates at
moderate energies are far higher
than expected from physical sputtering.
The same enhancement was also found in experiments
on the erosion of graphite or amorphous hydrocarbon
films (a-C:H) where the kinetic energy and the chemical
reactivity were supplied by two independent particle fluxes,
a beam of energetic argon ions and another flux of thermal
hydrogen atoms and explained by a rate equation model.
However, the adequacy of this phenomenologically derived
atomistic picture of the erosion mechanism was not clear.
Therefore, molecular dynamics simulations were performed to
gain insight into the atomistic erosion processes resulting in
the unexpected erosion enhancement. After preparation of an
amorphous C:H-sample with 930 atoms with an H/C-ratio
of 0.61 and a density of 1.7 g/cm 3 a comprehensive set of
bombardment simulations has been performed. The simulations
revealed an erosion mechanism which can be described
best as Hydrogen Enhanced Physical Sputtering (HEPS):
First, the energetic argon ions create dangling bonds within
the penetration range. Then the abundant hydrogen atoms
saturate most of the broken bonds in the first few atomic
layers. Subsequent Ar bombardment causes the breaking of
more C-C bonds. The steric repulsion which arises from H
atoms bound to neighboring C atoms in the top layer prevents
the recombination of broken C-C bonds. Finally, the release
of hydrocarbon molecules is caused by a physical sputtering
step. Hence, the emitted molecules are energetic radicals in
contrast to thermalized and saturated hydrocarbon molecules
suggested earlier. The observed HEPS mechanism is a
fast surface erosion process and the time scales are in the
picosecond range.
Characterization of a New Atomic Beam Source
A new beam source for atomic hydrogen was constructed
that will be applied for growth and erosion studies of amorphous
hydrogenated carbon films (a-C:H). The aim was to
develop a source that produces a quantified beam of low
energetic atomic hydrogen (H 0 ) or deuterium (D 0 ) with a
much higher flux than the presently used thermal source.
The new source is based on dissociation of H 2 (D 2 ) in a microwave
plasma. It promises higher flux densities as it features a
high degree of dissociation even at higher pressures. In addition,
a substrate in front of such a source would not be

exposed to thermal loads, as with the old source, and would,
therefore, allow much smaller working distances and consequently
higher flux densities. Furthermore, the source can
also be applied to produce atomic nitrogen as well as atomic
oxygen (using N 2 and O 2 as working gas, respectively)
which will be of interest for future work. The new source
was characterized with molecular-beam mass spectrometry
(MBMS) and with a catalytic sensor in terms of atomic flux
density produced as a function of gas throughput, microwave
power, and distance from the source. Both methods
were cross checked with the standard erosion method of an
a-C:H film at elevated temperature.
To achieve a high degree of dissociation the discharge is
ignited in a quartz tube. Quartz is used because the recombination
coefficient of H 0 (D 0 ) on quartz is very low at room
temperature. For sufficiently long tubes the particle flux
only consists of thermal H 0 (D 0 ) and H 2 (D 2 ) because the
energetic species thermalise due to collisions with the cold
walls of the tube before leaving the source.
The catalytic sensor consists of a 200 μm thin gold plated
nickel disc that is connected with two 25 μm thick thermocouple
wires of the K type and follows the design of
Mozetic. If H 0 (D 0 ) hits the sensor surface it can recombine
to H 2 thereby transferring part of the released binding energy
to the sensor. In equilibrium, the heating due to surface
recombination balances the cooling due to thermal conductivity
of the surrounding gas, thermal conductivity of the
probe, and grey-body radiation. For temperatures up to
500 K cooling by radiation can be neglected so that the temperature
is a direct measure of the flux of atoms onto the
probe tip surface. Because the recombination probability of
H 0 (D 0 ) on the specific surface, as well as the energy fraction
transferred to the sensor is unknown, the sensor is a priori
not suited for absolute measurements, but proved to be valuable
as it allows easy real-time measurements. Because the
sensor surface needs to be activated and can degrade with
time, cleaning by argon sputtering and atomic hydrogen in
vacuum is necessary to activate it and get reliable results.
Both methods reveal, that the H 0 (D 0 ) flux increases with the
flow of H 2 (D 2 ) and decreases with one over the square of the
distance from the exit orifice. Initially the flux increases with
microwaver power, but shows a maximum around 90 W. For
higher power the flux quickly decreases, possibly because
H 0 (D 0 ) recombines on the increasingly hotter tube walls. A
gas independent calibration procedure by reference signals
was developed to achieve absolute quantification of the atomic
flux with the quadrupole. For a tube with an inner diameter of
8 mm the maximum D 0 flux on the beam axis is 1×10 22 m -2 s -1
in a distance of 10 mm given a D 2 -flow of 100 sccm and
90 W microwave power. This flux is more than 2 orders of
magnitude higher than the flux that can be achieved with the
presently used sources which are based on thermal dissociation
of H 2 (D 2 ) in a resistively heated tungsten capillary.
Plasma-facing Materials and Components
72
Migration of Materials in Fusion Devices
Carbon Deposition in the Inner Divertor of ASDEX Upgrade
The deposition of carbon in the inner divertor of ASDEX
Upgrade was determined concomitantly to the transition from
a carbon-dominated machine in the discharge campaign
2002/2003 to a full tungsten machine in 2007. In the carbondominated
campaign about 15 g of carbon was deposited
on the inner divertor tiles in 3000 s divertor plasma time.
Coating of the upper divertor and the passive stabiliser loop
with tungsten did not significantly change the carbon deposition
in the inner divertor during the campaign 2004/2005.
A substantial decrease of the carbon deposition by a factor
of 5-7 was only observed after coating the ICRF protection
limiters with tungsten in 2005/2006. The remaining carbon
deposited in the inner divertor originated at least partly from
the outer carbon divertor tiles. The replacement of all remaining
carbon tiles at the inner and outer strike points by
tungsten coated ones resulted in a further decrease of carbon
deposition. A large fraction of the inner divertor changed from
a net carbon deposition area to an area without carbon deposition,
where only small residual amounts (about 20 nm) of
re-deposited carbon were observed. Some remaining carbon
deposition was observed below the inner strike point and at
the roof baffle just opposite to the inner strike point.
Electrical arcs burned through the tungsten layers in some
areas of the inner divertor resulting in some carbon erosion.
Beryllium Wall Sources and Migration in L-Mode Discharges after
Beryllium Evaporation in JET
The evolution of gross erosion flux, plasma concentration,
and divertor deposition of the wall constituents (Be, C) in the
JET tokamak has been investigated by spectroscopic measurements
of local Be and C sources and C plasma concentration
directly after 4h extended Be evaporation in a series of
identical 2.5 MA L-mode discharges with 1.5 MW neutral beam
heating. A plasma cross-section with high wall clearance
and divertor strike-points at the horizontal divertor plates was
chosen to optimise spectroscopic lines of sight and to avoid
excessive local erosion. Line intensities of Be II and C II
ions normalised to D α and D β emission of the local D recycling
flux provided information about the time evolution of relative
abundance and surface coverage of both wall materials.
Charge exchange spectroscopy was used to measure the evolution
of the carbon plasma concentration due to the changing
surface composition. In addition, impurity deposition in
the inner divertor was measured by a quartz microbalance.
The extended Be evaporation leads to an initial ≈8-fold
increase of the Be main chamber wall source over the pre-Beevaporation
level and a corresponding reduction of the carbon
source by a factor of ≈2. A similar increase of the Be
source is observed at the outer divertor target plate while in the
inner divertor, the Be source increased only by a factor of ≈3.

In contrast to the main chamber, divertor C sources were only
25 % lower than pre-Be-evaporation level. Both the carbon
wall and divertor sources, and the deposition rate in the inner
divertor increase to a stationary level within the first 3 discharges
still below the initial values before Be evaporation.
Correspondingly, one observes a steep decrease of the Be
sources in the first 3 discharges. In contrast to the carbon
sources, Be sources continue to decrease until the end of the
experiment although with a slower rate than in the initial discharges.
Also the carbon plasma concentration continues to
increase at this slower rate, which shows that unobserved carbon
sources, possibly at main vessel limiters or recessed wall
areas, contribute to the carbon plasma contamination. The Be
source in the outer divertor returns to almost pre-Be-evaporation
level while in the inner divertor the decrease is much less pronounced.
This confirms results of post-campaign analysis of
Be/C coverage on retrieved divertor tiles, which showed that
redeposition of low-Z elements generally prevails in the inner
divertor while the outer target plate is a region of net erosion.
DIVIMP simulations are on the way to interpret the results
and to derive a detailed model of the Be migration pattern.
Tritium Inventory – Understanding and Control
Retention of Deuterium in Tungsten
The ion-driven retention of deuterium in polycrystalline
tungsten was studied theoretically as a function of temperature,
incident ion energy, and incident ion fluence based on
experimental data obtained by thermodesorption spectroscopy
(TDS) and ion beam analysis. Three types of defects
have to be taken into account in order to explain the experimental
results: Intrinsic defects (dislocations, vacancies,
grain boundaries) distributed homogeneously throughout the
whole sample thickness, and ion induced defects (vacancies,
dislocations, deuterium clusters) within a shallow implantation
range (thickness about 100 nm) and ion induced defects
within a modified layer having a thickness of a few μm. Ion
induced defects in the modified layer extend much further
than the ion range, which can be explained by a stress field
induced by the deuterium concentration in the near-surface
layer. At high fluences an additional change of the diffusion
coefficient within the modified layer has to be assumed. This
allows a full description of all experimental observations
(TDS curves, deuterium depth profiles, fluence dependence,
temperature dependence, energy dependence of the amount
of trapped deuterium) with a single set of parameters.
Binding States of Deuterium Implanted into Beryllium
In the context of plasma−wall interaction of hydrogen ions
and beryllium as a first wall material for the future fusion
experiment ITER, the retention of 1 keV H + and D + ions implanted
into clean, single crystalline Be at room and elevated
temperatures is investigated by temperature programmed
Plasma-facing Materials and Components
73
desorption (TPD). Although many studies have been dedicated
to this issue in the past, details of the retention mechanisms
are still unclear, mostly because of oxidised sample surfaces.
In situ XPS measurements show, that the cleaned and
annealed Be sample has residual oxygen concentration
equivalent to 0.2 ML BeO in the near surface region as the
only contamination. Low energy ion spectroscopy (LEIS)
shows, that Be from the bulk covers thin BeO surface layers
above an annealing temperature of 1000 K by segregation,
forming a pure Be-terminated surface which is stable at lower
temperatures until again oxidised by residual gas. No hydrogen
is retained in the cleaned sample above 950 K. Annealing
the sample at 1000 K recrystallises the surface and thus heals
defects in the lattice. By analysis of TPD spectra, active retention
mechanisms and six energetically different binding states
are identified. Activation energies for the release of D from
binding states are obtained by modelling the experimental data
with TMAP7, a code that includes diffusion, trapping, and surface
processes. Together with literature values for solubility
and diffusivity, binding energies (E B ) for D in Be are obtained
(figure 1). Two types of ion induced trap sites (point defects)
with release temperatures between 770 and 840 K (E B =1.69
and 1.86 eV, states 3 and 4) are created at fluences below
1·10 17 cm -2 by the D implantation itself. 80 % of the implanted
hydrogen is trapped in these defects. Two trap sites (states 1
and 2, release between 440 and 470 K with E B =1.06 and
1.14 eV) are created due to local supersaturation of the bulk
above the local saturation concentration of 0.35 D/Be. Implantation
of H and D indicates, that the ion induced trap sites
are influenced by an isotope effect. None of the release steps
shows a surface recombination limit. A thin BeO surface layer
introduces an additional binding state with a release temperature
of 680 K (6). Implantation at elevated temperatures (up to
530 K) changes the retention mechanism above the saturation
limit. A phase transition due to the elevated substrate temperature
leads to the formation of increasing amounts of BeD 2 in
the supersaturated areas, which decomposes at 570 K (5).
Temperature [K]
300
400
500
600
700
800
900
1000
(5)
E
S
=
- 0.1 eV
(1) (2)
(6)
(3)
(4)
E
Desorption rate of
D 2 (m/q = 4) [a.u.]
∆ED = 0.29 eV
Mobile
state
- 1.69 eV
- 1.86 eV
- 1.06 eV
Ion-induced
defects
BeD2
Supersaturation
Be bulk
BeO-D
E0 = 0 eV
D atom
EBE (1/2 D2) =
- 2.28 eV
D2 molecule
Surface
∆EAdsorbed =
0.87 eV
Figure 1: Schematic energy diagram of the binding states of deuterium
implanted into beryllium (right side) and a typical TPD spectrum (left side).
The horizontal arrows assign the identified binding states to experimental
desorption peaks (1-6).

Ion Beam Analysis of Deuterium Retention in Be/D
Co-Deposited Layers
The co-deposition of Be and D will be a challenging problem
for ITER: Due to the large Be covered first wall area in ITER
and the high physical sputtering yield of Be plasma concentrations
of up to percent levels can be expected in the ITER
divertor. This results in an influx of Be and D onto the divertor
elements that can lead to deposition of thick Be layers containing
a fraction of D that depends on surface temperature,
particle energy and the Be flux fraction. The dependence of the
D/Be ratio on these parameters is yet unknown since a large
scatter in the available data exists. To remedy this situation dedicated
experiments have been performed at the PISCES-B
facility at UC-San Diego: A solid Be sample was exposed to a D
plasma and the eroded Be and D reflected from the sample were
collected on a temperature controlled disc that was shielded from
direct plasma impact. In these experiments the disc temperature
and D ion energy were varied. The Be/D ratio in the co-deposited
layers on these discs was analysed by ion beam analysis
at IPP. Both the Be and D areal density were measured using
nuclear reaction analysis (NRA) at the IPP tandem accelerator.
A2MeV 3 He ion beam was used to simultaneously measure
both the Be and D areal densities utilizing the Be( 3 He,p)B and
D( 3 He,p)a reactions, respectively. The energy of 2MeV was
chosen to yield a roughly constant cross-section for both
nuclear reactions through out the co-deposited layer. The typical
layer thickness was in the order of several hundred nm.
The NRA results showed that the Be/D ratio in these layers
varies from 0.005-0.7 depending on disc temperature and D
ion energy. Two general trends can be observed: The D/Be
ratio decreases with increasing deposition rate and increasing
temperature and it increases with D ion energy. This
behaviour can be qualitatively understood: High deposition
rates require a higher Be flux fraction onto the disc and thus
a lower D/Be ratio. High temperatures lead to an increased
loss of D due to effusion during layer deposition and therefore
results in a lower D/Be ratio. Higher D ion energy also
means that the reflected D that is co-implanted with the Be at
the collector disc has a higher energy resulting in a thicker
implantation zone and thus increased D accumulation.
Fuel Retention in ITER-Relevant Mixed-Materials
It is expected that mixed material layers will develop on the
wall surface of ITER resulting from the interaction of plasma
and plasma-facing materials (Be, W and CFC). The understanding
of hydrogen retention in such mixed material system is important
for a reliable extrapolation of in-vessel tritium retention
of ITER. In this study, D retention in “binary systems” and
ITER-relevant “mixed layers” (Be 2 C, Be 12 W and tungsten carbide)
was investigated under controlled laboratory conditions.
Binary system samples were prepared as thin films of about
200 nm on a substrate. The following film/substrate combinations
investigated in this study were: C/Be, C/W, Be/C,
Plasma-facing Materials and Components
74
Be/W, W/C, W/Be. C and W films were deposited by magnetron
sputter deposition and Be films by thermionic vacuum
arc deposition. Some of these samples were subsequently
annealed at defined temperatures for the fabrication of
mixed layers. 200 eV D ion implantation into the sample with
a flux of ≈3×10 19 D/m 19 s 1 was performed in the IPP High
Current Ion Source at room temperature. After reaching predefined
values of fluence (up to ≈4×10 24 D/m 2 ), the amount
of D retained in the samples was measured by nuclear reaction
analysis.
Figure 2: Fluence dependence of D retention in (a) carbon-coated samples,
(b) Be-coated and Be-related mixed layer samples and (c) W-coated and
W-related mixed layer samples, together with the literature data of each
pure material.
The results are summarized in figure 2. In the case of C or Be
coating, the D retention is predominantly determined by the film
with almost no influence of the substrate. This is probably
because D diffusion in C or Be at room temperature is negligible,
i.e. most of D is retained within the implantation range.
Eventually, D retention in the films saturates at a certain amount.

In both C and Be films, the D saturation level for 200 eV D
implantation is ≈7.0×10 20 D/m 2 . D retention in W coated
samples shows no clear saturation in this fluence range. On
the other hand, D bulk accumulation is inhibited, because at
room temperature D diffusion in the substrate material (Be
or C) is much lower than in W. As a consequence, the total
retention in the high fluence range in such thin W films is
lower compared to poly-crystalline (PCW) bulk tungsten.
D retention in Be 2 C, Be 12 W and tungsten carbide layers increases
with the incident fluence as ≈Φ 0.2 (Be 2 C, Be 12 W) and
≈Φ 0.4 (tungsten carbide), respectively (see figure 2b and c).
Moreover, D retention in Be 2 C and Be 12 W is comparable to
that of pure Be. Tungsten carbide shows similar fluence
dependence as PCW rather than graphite.
Permeation of Deuterium through Tungsten
The ion-driven permeation of deuterium through 50 μm thick
tungsten foils was investigated at elevated temperatures in the
range of 823-923 K, incident fluxes of 10 13 -10 14 D/sec/cm 2
and ion energy of 200 eV. The effective diffusivity for deuterium
transport through the samples is about four orders of
magnitude smaller than the classical Frauenfelder’s values.
This can be explained by the strong influence of defects.
Simulation calculations using the TMAP-7 code give a detrapping
energy of about 2.3 eV for these defects, and these
high-energy traps govern the diffusion process in the investigated
temperature range. The recombination coefficients for
the front and back sides have also been estimated. Sputter
cleaning of the surfaces increases the recombination coefficient
by several orders of magnitude.
Materials – Processing and Characterisation
Structural Investigation of Metal-Doped Carbon Films
Doped carbon materials show strongly reduced erosion yields
compared to pure carbon. This is due to an influence on the erosion
mechanism and the successive formation of a protective
metal-enriched surface region. Amorphous metal-doped carbon
films (a-C:Me) have recently been used for systematic erosion
studies. To investigate the influence of the film structure on the
erosion process, basic information about the metal distribution
and the structure of the carbon matrix is required. Therefore,
the structure of a-C:Me films was systematically analysed.
The investigated parameters were type of doping metal
(Me=W, Ti, V, Zr), metal concentration (

In previous experiments it was demonstrated that W alloys containing
Si form a protective SiO 2 layer in air at elevated temperatures,
which reduces the oxidation rate. Using the ternary
alloys W-Si-Cr, W-Si-Y, and W-Si-Zr, the oxidation behaviour
was further improved. The Arrhenius plot in figure 3 shows the
comparison of the oxidation rates k (= mass gain due to oxidation
per square centimetre and second) of pure tungsten, binary, and
ternary alloys at different temperatures. The contents of the additives
are given in weight percent in the alloy notation. From
the investigated samples the WSi8Cr12 alloy shows the highest
reduction of k by more than two orders of magnitude in the
whole investigated temperature range from about 900 to 1300 K.
The oxidation rate of this Cr-doped alloy is about a factor of
10 lower than that of the corresponding Cr-free alloy WSi13.
MoS 2 Coatings for W7-X
During operation of the W7-X stellarator, high forces act between
the superconducting coils. Therefore the coil casings are
reinforced among each other by narrow support elements (NSE).
For the pads inside the NSEs, a lubricant coating had to be developed,
which works in high vacuum under cryogenic temperatures
and which withstands the loads. Another challenge
was, that the coating has to ensure the expected lifetime of
W7-X without access for service and maintenance of the
NSEs after assembly of the experiment.
The materials research division of IPP Garching developed an
anti-friction MoS 2 coating which meets these requirements.
The applied MoS 2 coating is very thick (about 8 μm) compared
to the usually applied coating thicknesses of about 1 μm.
Nevertheless the MoS 2 layers show no columnar structure.
This is important, because columns will break under load.
Tests under high loads confirmed/approved that the coating
will protect the pad surface for the designated lifetime.
Transfer of the specific sputter deposition parameters to industrial
scale was not successful. The MoS 2 layers provided by
industrial partners showed columnar structure, lower lifetime,
and unsatisfying adhesion properties. Therefore, all NSE pads
for W7-X will be coated at IPP Garching using the available
magnetron sputter device.
Metal Matrix Composites
In future fusion reactors like DEMO, the fusion plasma leads to
a heat flux of typically 15 MW/m² in the divertor region. The
heat has to be removed efficiently from the plasma-facing
material (W, C) through the copper-based heat sink to the cooling
channels. According to the power plant conceptual study
(model A), it is desired to increase the cooling water temperature
to at least 300 °C for efficient energy production. Depending
on the divertor design, this will lead to high temperatures of up to
550 °C at the interface between plasma-facing material (W, C)
and heat sink material (Cu, CuCrZr). The mechanical properties
of the current Cu-based material at this high temperature are
insufficient. Additionally, due to the temperature gradient and
Plasma-facing Materials and Components
76
different coefficients of thermal expansion (CTE) of W and Cubased
materials, high stresses occur at the interface of PFM and
the heat sink material. The metal-matrix composite (MMC)
W-fibre-reinforced Cu has the potential to strengthen this zone
and shows great promise to improve the mechanical performance
at high temperatures compared to conventional Cu-based
alloys. The focus was placed on the optimization of the interface
to achieve an enhanced adhesion between W fibre and Cu
matrix. Five different interfacial concepts (e.g. pure copper
PVD interlayer, a graded transition PVD interlayer from
100 % W to 100 % Cu) and six different microstructuring concepts
(e.g. chemical etching, ion etching, fibre twisting) were
chosen to modify the tungsten fibre surface to achieve enhanced
interfacial adhesion. The interfacial properties were investigated
through pull-out measurements of single matrix-coated
fibres. Concerning the different interfacial concepts, up to 6 fold
increase in shear strength was achieved by depositing a graded
transition between W and Cu plus additional heat treatment.
Regarding the different microstructuring concepts, the highest
effect on interfacial adhesion between Cu and W (up to 3 fold
increase in shear strength) was achieved by fibre twisting to 30°.
Additionally, multi-fibre metal-matrix composites with the
best interfacial concept were synthesized using the Matrix-
Coated-Fibre (MCF) procedure. Discs of the MMCs were
thermally cycled between 350 °C-550 °C to investigate the
thermal stability and the behaviour of the fibre-matrix interface
which can be critical due to the CTE mismatch of W and Cu.
After 120 cycles no debonding of the W fibre from the Cu
matrix was observed. Therefore, the thermal stability of the
MMC in thermal cycling tests can be assured by depositing
a stepwise graded transition between W fibre and Cu matrix.
Figure 4: SEM images of the twisted and chemical etched W fibre a) and its magnification
b) used to achieve enhanced interfacial adhesion in a copper matrix
Component Behaviour
Probabilistic Failure Assessment of an Embrittled Tungsten
Divertor Structure
Inherent brittleness and neutron embrittlement are the most
critical weaknesses of tungsten for fusion application. Pronounced
scattering of the fracture strength of tungsten requires

a statistical treatment. Thus, the risk of structural failure of a
tungsten component can be estimated only in a probabilistic
framework. To this end, we applied a probabilistic failure analysis
code STAU to estimate the performance of a water-cooled
tungsten mono-block divertor component. The STAU code is
based on the weakest-link failure theory and linear elastic fracture
mechanics. A heat flux load of 15 MW/m² and a coolant
temperature of 320 °C typically expected for a water-cooled
fusion reactor were considered for the FEM stress analysis.
The failure probability was computed considering various
fracture criteria. Both the experimental (unirradiated tungsten)
and hypothetical Weibull parameters were used as material
data. The measured parameters were 31 (shape modulus) and
2353 MPa (scale parameter), respectively. The hypothetical
shape parameters ranged from 5 to 20 whereas the assumed
scale parameters from 1500 to 2500 MPa. In the case of unirradiated
tungsten, the failure probability was acceptably small
ranging from 0.025 % (surface cracks) to 0.08 % (volume
cracks). When either the Weibull modulus or the scale parameter
was hypothetically reduced, the resulting failure risk was
significantly increased far beyond a tolerable level. This result
clearly demonstrated the essential impact of embrittlement
on the failure behaviour. The most dangerous regions were
identified to be the narrow stress concentration domains
near the free surface edge of the bond interface between the
tungsten block and the copper cooling tube.
High Heat Flux Test Facility GLADIS: Test of W7-X-Target
Elements
The aim of the GLADIS facility (Garching LArge DIvertor
Sample test facility) is to provide thermal testing capabilities
for highly heat loaded divertor components which have both
active water cooling and large outer dimensions. In 2007,
approximately 35,000 pulses of typically 10 to 25 MW/m 2
heat flux density and pulse lengths between 10 s and 45 s have
been applied on the test samples. The technical improvement
of the facility resulted in a further extension of pulse length and
pulse repetition rate, respectively. As a new option a helium
beam can be generated with similar parameters in addition
to the hydrogen neutral beam for standard operation.
The main tasks of GLADIS in 2007 were the continuation of
thermo-mechanical qualification test for the actively cooled
W7-X pre-series divertor target elements and the participation
in the JET ITER-Like Wall Project to qualify the industrial
W coatings of CFC tiles.
More than 65 % of GLADIS operation time was dedicated to
high heat flux testing of a new set of W7-X pre-series divertor
targets. As most important result of the high number cyclic
loading tests can be summarized that a sudden defect of the
divertor due to loss of CFC tiles does not have to be expected
during plasma operation in W7-X. In previous test campaigns
of more than 30 full-scale elements the heat removal capability
of the W7-X target concept (flat tiles of CFC NB31 as plasma
Plasma-facing Materials and Components
77
facing material bonded by an Active Metal Casting (AMC ® )
copper interlayer onto a water-cooled CuCrZr structure) has
been demonstrated for the envisaged operational power load of
10 MW/m². No large detachment or loss of CFC tiles occurred
during cyclic loading tests at 10.5 and 13 MW/m², but growing
local debonded zones at the free edges of several CFC
tiles were observed on the previous prototypes.
As a consequence, detailed 3/D non-linear thermo-mechanical
FEM analysis of the system of CFC/Cu bonding with respect to a
further reduction of the stress at the CFC/Cu interface were
carried out by the manufacturer PLANSEE SE. As result a set of
17 additional pre-series elements was manufactured to investigate
the thermo-mechanical behaviour of the three most promising
design variations (for further information see chapter 3 –
Wendelstein 7-X, section 3.5.1 – Target Modules). For the preferred
design variation with the insertion of an additional compliant
Cu interlayer between AMC ® and CuCrZr cooling structure,
so called “bi-layer” and shown in figure 5, a 50 % reduction
of stresses and strains in the CFC/Cu interface was predicted.
Figure 5: Cross section of CFC/Cu bonding of bi-layer type after 5000
cycles 10 MW/m². The image clearly shows the good joining quality of the
Cu interlayer and the good CFC/AMC® bonding.
The extended cycling of two elements with more than 5000
cycles at 10 MW/m 2 confirmed the significantly higher reliability
of this type of CFC bonding. The targets were loaded with a
Gaussian heat flux distribution to study the evolution of bonding
defects depending on cycle number and local heat load. A
target length of 75 mm was loaded with 10 MW/m² on average,
the surfaces close by with load profiles between 9-7.5 MW/m².
The results of IR examination during these heat loading tests
are summarized in figure 6. For six identified growing hot
spots, the measured local surface temperature increase is correlated
to an expected size of debonding at the CFC/Cu interface
on the basis of thermal FEM calculations. The metallographical
analysis after testing confirmed that all observed growing hot
spots originated from a CFC/Cu de-bonding on the free edge.
The predicted de-bonding sizes of small hot spots are in
good agreement with the metallographically measured sizes.
The defects D1 and D2 were identified as slowly growing
defects for the applied heat flux density of 10 MW/m². For the
largest failure D1, the measured CFC surface temperature of
1755 °C after 5000 cycles of 10 MW/m² should be acceptable

for operation in W7-X. Growing defects were clearly detected
in an early stage of 10 MW/m² HHF testing. The defects D5
and D6, 10 MW/m² loaded as well, are very small and practically
stable defects. No significant progress of existing debonding
was observed for heat loads

Plasma Theory

Tokamak Physics Division
Head: Prof. Dr. Sibylle Günter
Tokamak Edge Physics Group
Work in the group has balanced
the use of existing codes to understand
phenomena in the edge plasma
(or to identify discrepancies
between code and experiment),
and the improvement of the codes.
Current edge codes form an important
bridge between results
on present machines and divertor operation on ITER. The
present ITER divertor is based to a large extent on the results
of simulations with one of the existing edge codes, while a
number of edge codes are in use to understand present day
experimental results. To place the ITER predictions on a
firmer footing, an effort has been made to verify the existing
codes by careful code-code comparison, and then to validate
the codes against the experiment. This is done within the
framework of an ITPA DivSOL activity (DSOL-14), and
also as part of the activities of the EU Task Force on
Integrated Tokamak Modelling. In 2004, the results of the
EDGE2D-NIMBUS, B2-EIRENE (SOLPS5) comparison
for the D only case were reported together with some preliminary
results with drifts. During the 2007 JET edge modelling
campaign, these results were extended to D+C for
SOLPS, and some results for D and D+C for EDGE2D-
NIMBUS and EDGE2D-EIRENE were also obtained. One
of the major results was a renewed look at the atomic
physics being used in the edge codes. For one particular
case, the peak target electron temperature was found to
change by a factor of nearly 10 depending on the choice of
atomic physics (for hydrogen).
In-depth examination of earlier identified discrepancies
between SOLPS modelling and AUG experimental data was
continued. Three types of discrepancies – in the divertor
electron temperature T e , radial electric field E r and Mach
numbers of parallel ion flow in the main scrape-off layer
(SOL) M || – were linked together. A consistent picture of the
problems encountered by the code modelling has been confirmed.
The leading assumption about the origin of the discrepancies
is the neglect of kinetic effects in the parallel electron
heat transport from the SOL to divertor. Analysis of publications
related to the role of kinetic effects in the SOL reveals
a significant effect which they can have on the electron distribution
function near the target, resulting in higher parallel
electron heat flux and a large Debye sheath drop at the target.
Work has started on developing a kinetic treatment for the
edge plasma, with the intention of either coupling this to B2,
or to try to parameterize the results in some fashion for
inclusion in the fluid plasma code. In continuation of a project
on disruptions at JET, a series of modified pre-disruptive
Theoretical Plasma Physics
Head: Prof. Dr. Per Helander
The project “Theoretical Plasma Physics” is devoted
to first-principle based model developments
and combines the corresponding efforts of
the divisions Tokamak Physics and Stellarator
Theory, of the Junior Research Groups “Turbulence
in Magnetized Plasmas”, “Theory and Ab Initio
Simulation of Plasma Turbulence”, and “Computational
Material Science”, and the EURYI Research
Group “Zonal Flows”. It is headed by one theorist
on the board of scientific directors at a time.
81
JET equilibria has been subjected
to thermal quench modelling
with the SOLPS package.
Development of version 6.0 of
the SOLPS package supporting
adaptive mesh refinement has
continued. Based on the current
implementation of the B2 fluid
code, approaches to implement a
generalized framework for the solution
of the fluid equations have
been studied. The main focus lies
on higher-order schemes for conservation laws on unstructured
quadrilateral meshes and efficient data structures enabling
later parallelization of core components of the code.
Other work included: (1) continuing activities associated
with the EFDA Task Force on Integrated Tokamak Modelling;
(2) maintenance, support, and further development of
the SOLPS code; (3) supporting the use of SOLPS at IPP to
(i) explore the differences between L- and H-mode edge profiles
in terms of the derived transport coefficients, (ii) explore
the impact of a killer gas puff on AUG, and (iii) explore the
process of detachment.
MHD Theory Group
Heat Transport in Magnetic Islands
Heat diffusion studies using a recently developed numerical
scheme were continued. For cylindrical geometry, heat diffusion
across magnetic islands and ergodic layers has been
studied in detail. The effect of the observed island temperature
flattening on the stability of Neoclassical Tearing Modes
was examined. It was found that the neoclassical island drive
is significantly stronger for realistic island parameters than
predicted by Fitzpatrick 1 .
A new code has been implemented which applies the numerical
scheme to toroidal geometries using straight field line
coordinates. First results for magnetic islands and ergodic
layers in realistic ASDEX Upgrade equilibria suggest that
cases with realistic heat diffusion anisotropies can be very
well resolved.
Fully Three-dimensional Resistive Wall Mode and Feedback
Stabilization Studies
The feedback stabilization of Resistive Wall Modes (RWMs)
has been studied in the presence of multiply connected wall
structures using the fully three dimensional CAS3D, STAR-
WALL, and OPTIM codes. The coupling of toroidal modes
in 3D has been taken into account. The codes have been
applied to an ITER and an ASDEX Upgrade like equilibrium
with β N =2.51 and β N =2.62, respectively. For both cases stable
solutions have been found.
1 R. Fitzpatrick, Physics of Plasmas 2, 825 (1995)

While for the ITER wall the mode coupling is negligibly small,
the complex structure of the additional AUG wall segment leads
to a significant coupling of the n=1 and n=2 toroidal harmonics.
Furthermore, the feedback optimization code OPTIM has
been supplemented with a robust control package. Eigenvalue
sensitivity is now taken into account by the concept of
pseudospectra. The computed feedback controllers are optimally
robust with respect to, e.g., model imperfections, and
transient amplifications of initial perturbations are kept at a
moderate level.
Preliminary investigations indicate that both robustness and
transient growth could be a severe issue when attempting to
stabilize RWMs in ITER.
Kinetic MHD and Fast Particle Physics
A comprehensive and self-consistent kinetic investigation of
global fast particle driven modes in tokamak plasmas below
the toroidal Alfvén Eigenmode (TAE) frequency requires
the inclusion of the bulk ion compressibility. This extension
enables the linear gyro-kinetic eigenvalue code LIGKA to
analyse the low-frequency properties of the Alfvén cascade
modes (AC), the beta-induced Alfvén eigenmodes (BAE)
and the energetic particle modes (EPM). Furthermore, also
the linear phase of micro-instabilities like ion-temperaturegradient
modes, trapped-particle modes or micro-tearing
modes can now be described with LIGKA. Thus, it closes
the gap between global low-n MHD descriptions and high-n
micro-scale turbulence codes (in their linear phase). As an
application, the kinetic damping mechanisms of the resistive
wall modes have been investigated. It was found that not
only the sound wave damping near the rational surfaces contributes
but also the coupling to the electrostatic drift branch
modifies the mode structure and therefore modifies the
damping rate.
Linear MHD Stability Analysis
Within the Integrated Tokamak Modelling effort (IMP#1), a
matching suite for optimized linear MHD stability analysis
has been created by improving and adapting the converter
tool RWSHOT for experimental shotfiles, the fixed boundary
equilibrium code HELENA, and the linear MHD stability
code ILSA.
It is now possible to calculate the linear MHD spectrum of
edge modes vs. their toroidal mode number starting from
free boundary equilibria generated by the equilibrium codes
CLISTE and EFIT, thereby facilitating comparison of most
major tokamak devices in the fusion community. In the light
of this new possibility, benchmarking studies of edge stability
have been carried out at DIII-D and ASDEX Upgrade,
highlighting the influence of near-X-point geometry on the
stability of the peeling-ballooning mode. While there is
good agreement on the stability of the ballooning term,
results with respect to the pure peeling and kink terms
Theoretical Plasma Physics
82
remain inconclusive due to numerics limitations in the
vicinity of the X-point. Further, potentially analytical, effort
is needed to elucidate on the relevance of the peeling mode
in strongly sheared geometries.
Non-linear MHD Studies
The locking of neoclassical tearing modes (NTMs) by error
fields was studied numerically. In the regime with low mode
frequency and large plasma viscosity, the required field
amplitude for mode locking is found to be proportional to
the plasma viscosity and the mode frequency but inversely
proportional to the square of the magnetic island width and
the Alfvén velocity, indicating that NTMs will be locked to
low amplitude error fields in a fusion reactor. The stabilization
of NTMs by RF current in the presence of a static helical
field was therefore further investigated. The applied helical
field allows controlling the location of the island’s o-point
to be in the RF wave deposition region, to enable the NTM
stabilization by RF current after mode locking. When the
island is large enough to be locked by a small amplitude helical
field in the desired phase, the island is reduced to a
smaller width by RF current compared to the case without
the helical field. This suggests a possible way to enhance the
stabilization of NTMs by RF current.
The error field (or externally applied helical field) penetration
was studied numerically based on the two fluids equations.
It was shown that there is a minimum in the required
field amplitude when the applied helical field frequency is
the same as the mode frequency being determined by both
the background equilibrium plasma rotation and the diamagnetic
drift. The mode penetration threshold significantly
increases as the field frequency deviates from the mode frequency
and can become asymmetric on both sides of the
minimum due to parallel transport. After mode penetration,
the non-linear saturated island width is found to be smaller
for larger electron diamagnetic drift frequencies.
Transport Analysis Group
In the field of core transport, work has been dedicated to
understanding the central behaviour of Si laser ablated impurities
in response to localized central electron heating in
AUG H-mode plasmas with a background of NBI heating.
The Si impurity central profile flattens in response to central
electron heating up to exhibiting a hollow profile which cannot
be explained by neoclassical theory. The gyrokinetic
code GS2 has been used to calculate the turbulent transport
of the Si impurity under these experimental conditions.
It has been found that in the presence of strong central electron
heating, modes rotating in the electron diamagnetic drift
direction are destabilized in the central region of the plasma,
generated by the non-adiabatic response of passing electrons
and featuring extremely elongated eigenfunctions along
the field lines. The related fluctuations in the electrostatic

potential generate an outward convection of the impurities
which is in agreement with the outward convection of Si
measured under these experimental conditions. By contrast,
in the outer region of the plasma, as well as everywhere in
the absence of central electron heating, ion temperature gradient
modes produce an inward impurity pinch, which is
also in agreement with experimental observations.
In the framework of transport modelling, simulations of
ITER and DEMO scenarios have been continued. The question
which has been answered is whether a theory-based transport
simulation can be characterized by a fixed enhancement
factor with respect to the H98(y,2) confinement scaling.
It is found that although a noticeable concurrence is observed,
this is no more than an occasional coincidence. The
scaling and theory-based predictions show very different
parameter dependences and there is no simple recipe to
replace one by the other. During this work, a new numerical
algorithm has been developed that allows for an increase of
the speed of computations by orders of magnitude and
enables massive parametric studies with theory-based stiff
transport models.
Kinetic Theory and Wave Physics Group
We have completed the implementation of a realistic NBI
source in the SSFPQL Fokker-Planck solver embedded in
the TORIC package. This was motivated by ASDEX
Upgrade experiments, suggesting a 2 nd -harmonic heating of
NBI deuterons in the neutron rate time trace. We have
improved the algorithms and added toroidal effects on the
RF quasi-linear operator.
To close the consistency loop between the TORIC full-wave
solver and the Fokker-Planck module, we have started to
modify the interface for the evaluation of the coefficients of
the wave equation in the presence of non-Maxwellian distribution
functions.
We have updated and optimized the full-wave code FELHS
for lower hybrid (LH) waves in slab geometry. This code
estimates the grill coupling efficiency for general density
and magnetic field profiles. It is currently used by the POLITO
group (Torino, Italy) to obtain the plasma response in their
antenna code for the evaluation of the coupling efficiency of
LH launchers.
The propagation of LH waves in toroidal plasmas can be
computed employing the beam tracing technique, which reduces
the wave equation to a set of ordinary differential
equations (thus reducing the computational effort) retaining
diffraction effects. The diffractive broadening of the beam
is believed to provide a mechanism for filling the spectral
gap between the electron thermal velocity and the phase
velocity of the wave. To this aim, the code LHBEAM has
been developed. It solves the beam tracing equations in
tokamak geometry for arbitrary launching conditions and
for analytic magnetic equilibria. First results show a signifi-
Theoretical Plasma Physics
83
cant broadening of the LH beam for parameters typical of
present-day experiments. The evaluation of the resulting
wave-number spectrum is under way.
The expulsion of fast trapped ions generated during IC heated
discharges has been investigated. Losses of energetic particles
with gyroradii above 4 cm have recently been observed
in ASDEX Upgrade and have been shown to be related to
low-frequency MHD modes like NTMs.
The loss mechanism is found to be connected to the drift of
the ions along the perturbed magnetic field, which acquires
a preferential radial direction if the bounce frequency is close
to a multiple of the toroidal precession frequency. This mechanism
also explains the phase modulation of the particle-loss
signal. Numerical simulations performed with the HAGIS
code show good agreement with experimental results.
Development of Mathematical Tools
Mathematical models for anomalous transport were considered.
In particular, a quasi-linear heat equation with only
piecewise differentiable coefficients was investigated further.
Existence of solutions with a moving free boundary was
proven under milder assumptions than previously.
Also, matrix-free iteration schemes for the solution of large
non-linear parameter-dependent systems were investigated
further. If Picard iterations cease to converge at a certain
parameter value, it almost always helps to split the solution
manifold: Newton iterations on a small invariant subspace,
Picard iterations on the large remainder.
Turbulence Theory Group
We continue to study low frequency fluid like drift turbulence
employing gyrofluid models extended to capture
important kinetic effects such as Landau damping and finite
gyroradius (FLR), as well as gyrokinetic models, treating all
phenomena at the scales of interest (1 mm to 10 cm, 10 kHz
to 1 MHz). Both types of model have been recast for greater
accuracy within a wider set of parameter regimes. The
gyrofluid model GEM and the gyrokinetic model dFEFI are
intended to treat equilibrium and turbulence phenomena
together at all collisional regimes, as especially needed for
the tokamak edge. The gyrokinetic particle in cell code
ORB5 is intended to treat global core turbulence and will
attempt full-scale ITER simulations in 2008.
Gyrokinetic/Gyrofluid Studies of Core Turbulence
The ORB5 model treats the plasma as a set of marker particles
sampling the phase space on a discrete basis. ORB5 is
one of the codes advancing the state of the art on PIC methods
in global gyrokinetic computation in this decade. Work on
hyperfine scale electron temperature gradient (ETG) turbulence,
occurring at scales below the ion gyroradius, was
completed in 2006 and published in early 2007. Ion temperature
gradient (ITG) turbulence was the focus for 2007.

Generally, ITG turbulence is more difficult computationally
because it generates large scale “zonal” flows (“zonal”
refers to the flux surface average component). These flows
represent the perturbed equilibrium and are involved in geodesic
acoustic oscillation “modes” (GAMs). They serve to
moderate the turbulence and represent a long-term background
phenomenon to which the turbulence is coupled.
Hence, runs must be longer and noise and saturation issues
increase the difficulty. In 2007 the massively parallel scaling
properties of the code were improved and it now runs reliably
on at least 10,000 processors. A novel diagnostic to
quantify the noise issues was developed; recent cases are
run to saturation with the noise in the range of 5 percent.
Kinetic electrons have been included. A run on 10 k processors
on the Edinburgh Hector platform found well behaved
long term saturation and converged scale separation
(between turbulence and profile relaxation). In 2008 the
Alfvén dynamics will be tested and full scale ITER cases
will be run.
Global electromagnetic computations of ITG/Alfvén turbulence
were run using GEM for various tokamak sizes.
For domain sizes of at least 200 ion gyroradii complete
scale separation was found: the turbulence no longer has
any effect on the profile of poloidal (specifically, E×B)
rotation. The rotation profile is determined by neoclassical
effects (balances between parallel forces/divergences and
magnetic drifts). For JET and ITER scale (400 or 800 gyroradii)
even the details of the profile shape change only on
transport time scales. In the course of this work the GEM
code was improved so as to scale to 512 processors on the
IBM Regatta architecture at well over 80 percent efficiency
Theoretical Plasma Physics
84
in the hard scaling. Similar performance up to 2048 processors
on the new Blue GENE/P was achieved.
Gyrofluid/Gyrokinetic Studies of Edge Turbulence
The study of self consistent geometry up to now requires
analytical models for the metric. Changes in the q-profile
and the Shafranov shift due to the background currents and
pressure profile are followed. This model was extended to
include proper separatrix geometry, which will be incorporated
into the GEM code.
Several series of parameter scalings were run using both
GEM and dFEFI in fluxtube mode (radially local gyrofluid
and phase space gyrokinetic treatments of the same problem
set) to test hypotheses involving temperature scaling of
sheared equilibrium E×B rotation and turbulence. A weak
dependence of shear suppression on temperature and flow
shear was found, but too weak to overcome the larger ρ ∗ at
higher temperatures.
The ideal MHD instability scenario for ELM events was
investigated using GEM. In contrast to other studies using
MHD models, GEM also treats the generic drift wave turbulence
down to and below the ion gyroradius scale. No threshold
was found because the turbulence remains driven by
temperature gradients (both species) when the ideal ballooning
instability is absent. The transition to MHD dominance
is gradual. Converged cases are found only when the spectrum
reaches all the way down to the ion gyroradius. The time
scale and energy content of the blowout are commensurate
with experimental observations, but the scenario remains a
hypothesis because clearly self consistent representations
of the H-mode state are still lacking.
Figure 1: Electron density contours before, during, and after an ideal ballooning mode blowout. The original instability has toroidal mode numbers 7-9, visible at
the beginning of the event. The blowout eventually saturates upon its own self-generated turbulence, whose scale range reaches down to the ion gyroradius.
Work carried out in collaboration with A Kendl, Uni Innsbruck.

Fundamental Theory
The proper form of magnetic non-linearities in gyrofluid
equations which treat electron gyroradius effects was
worked out. These equations can be used for reconnection
studies which involve non-linearly generated current sheets
on the plasma skin depth and electron gyroradius scales.
The complete derivation of the reduced MHD equations
from fully non-linear (“total-f”) gyrokinetic field theory was
worked out. Improved numerical schemes using this as a
splitting method are under investigation.
EU-Task Force on Integrated Modelling
We are participating intensively in the turbulence benchmarking
projects under the auspices of the EU Task Force
on Integrated Tokamak Modelling. B Scott is the Project 4
leader.
Scientific Staff
C. Angioni, A. Bergmann, R. Bilato, A. Bottino, M. Brüdgam,
A. Chankin, D. Coster, A. Dodhy-Würsching, S. Gori,
S. Günter, M. Hölzl, O. Kardaun, H.-J. Klingshirn, C. Konz,
K. Lackner, P. Lauber, P. Martin, P. Merkel, R. Meyer-
Spasche, G. Pautasso, G. Pereverzev, E. Poli, T. Ribeiro,
W. Schneider, E. Schwarz, B. Scott, M. Sempf, M. Siccinio,
H. Siddiqui, E. Strumberger, C. Tichmann, C. Wigger, Q. Yu,
R. Zille.
Guests
C. V. Atanasiu, Institute of Atomic Physics, Bukarest, RO;
N. Bertelli, University of Pavia, IT; O. Maj, University of Pavia,
IT; P. McCarthy, University College, Cork, IR; G. J. Miron,
Institute of Atomic Physics, Bukarest, RO; E. Quigley, University
College, Cork, IR; V. Rozhansky, Technical University,
St. Petersburg, RU; G. Sias, RFX Consorzio, IT;
G. N. Throumoulopoulos, University of Ioannina, GR;
S. Voskoboynikov, Technical University, St. Petersburg, RU;
H. Weitzner, Courant Institute, New York, USA.
Theoretical Plasma Physics
85
Stellarator Theory Division
Head: Prof. Dr. Per Helander
During 2007, Jürgen Nührenberg retired from his post as head
of the Stellarator Theory Division, and the W7-X Applied
Theory Group was incorporated into the Division.
ITG Turbulence Simulations
Ion-temperature-gradient turbulence constitutes a possibly
dominant transport mechanism in optimized stellarators, at
least in some regions, in view of the effective suppression
of neoclassical losses characterizing these devices. The gyrokinetic
code GENE has been extended to work in general
geometry and nonlinear turbulence simulations for W7-X
have been performed, assuming an adiabatic electron response.
Several interesting results have been found, including
the role of zonal flows for turbulence saturation, the
resulting flux-gradient relationship, and the coexistence of
ion-temperature-gradient modes with trapped ion modes in
the saturated state.
Global Gyrokinetic Simulations
The particle-in-cell code EUTERPE which is used for the
global simulation of linear ITG modes in stellarator geometry
has been extended to allow for the inclusion of density gradients.
Since a radial electric field can also be prescribed it
is now possible to run simulations under realistic conditions.
When the electron response is adiabatic the equation for the
electric field consists of a Helmholtz operator plus a nonlocal
term given by the flux surface average of the electrostatic
potential. This term is important to correctly capture
the behaviour of zonal flows which are important for nonlinear
simulations. While the matrix representation of the
Helmholtz operator is sparse that of the averaging operator
leads to a dense matrix. To overcome the related memory
problems a new solver has been developed which treats the
non-local term as matrix-free in the context of preconditioned
iterative solver methods. As an application for this
new solver the Rosenbluth-Hinton test was performed for
tokamak configurations with different aspect ratio and elongation.
It was found that the residual flow level increases
with increasing elongation or decreasing aspect ratio in
good agreement with semi-analytical theory. To perform
global simulations of turbulence, a non-linear version of
EUTERPE has been developed. Scalability has been demonstrated
for up to 512 processors, which is a prerequisite for
non-linear simulations.
Plasma Rotation in Stellarators
The conditions were investigated under which rotation
comparable to the ion thermal speed may occur in threedimensional
equilibria. For tokamaks, it is well known that
the plasma can rotate toroidally but not poloidally if the ion

gyro-radius is small. The corresponding question for stellarators
had, however, not been answered. It turns out that
rapid plasma rotation is only possible in a certain class of
magnetic fields where the magnetic field strength depends
on the arc length along the field in the same way for every
field line on the same flux surface. In particular, quasiaxisymmetric
and quasi-helically symmetric magnetic
fields fulfil this condition. Moreover, the plasma flow must
be in the direction of constant magnetic field and tangential
to the flux surfaces.
Resistive Stability in Plasmas with Runaway Electrons
In tokamak disruptions, the Ohmic current is often replaced
by a current of runaway electrons which is likely to be
peaked more strongly in the centre of the discharge than the
pre-disruptive current. This raises the question of the resistive
stability of the post-disruption plasma where the equilibrium
current is entirely carried by the runaway electrons
while the cold (

as the background magnetic field the Alfvén continuum
frequency can lie in the range of the diamagnetic frequency
of the background electrons. If the electron diamagnetic
frequency exceeds the mode frequency an unstable drift-
Alfvén wave arises due to the coupling between the drift
and Alfvén waves. The coupling occurs through the parallel
electric field and the mode is destabilized due to parallel
resonances such that this phenomenon can be described in
screw pinch geometry. Since the mode is non-perturbative
its growth rate can be large and comparable to the real part
of the mode frequency. The growth rate usually attains its
maximum at a small mode number such that the most
unstable mode can appear to be global and may be confused
with, e.g., a global Alfvén mode (GAE).
Ideal MHD
The ideal MHD stability code CAS3D was generalized to
be used for the calculation of a perturbed equilibrium
which is provided by the linear ideal stability theory as the
plasma response to a small perturbation of an equilibrium
state. In this approach magnetic islands may be characterized
by a surface current. The CAS3D results were successfully
benchmarked vs. a code for the ideal cylindrical stability.
In stellarator geometry, the shift of the magnetic
surfaces due to a plasma-beta increase, computed by
CAS3D, compares well to results gained from the VMEC
equilibrium code.
Kinetic MHD
The CKA code (to calculate Kinetic Alfvén waves in stellarators)
has been further developed and benchmarked. It
employs a reduced MHD model with finite Larmor radius
effects. So far, relatively good agreement with ideal MHD
has been achieved. To allow the calculation of fast particle
interaction with waves a reorganisation of the CAS3D-K
code has begun. In its new structure the code has been
applied to zonal flow physics.
Development of Stellarator Concept
In quasi-isodynamic configurations, the divergence of the
current density perpendicular to the magnetic field lines
changes sign only once along the magnetic field within one
field period. This implies that the parallel current density
cannot change sign along the magnetic field. Thus, because
of the vanishing net parallel current, the parallel current
density exhibits a dipole component which impairs MHD
stability at very high-β. In this work, a new structure of a
period has therefore been introduced in which the B contours
change their inclination with respect to the orthogonals
to the field lines along the magnetic field within half a
period. This makes it possible to eliminate the dipole component
of the parallel current density whilst keeping the second
adiabatic invariant constant.
Theoretical Plasma Physics
87
Applied Theory Group
Bootstrap Current Benchmarking
In the benchmarking of mono-energetic bootstrap current
coefficients, two different Monte Carlo codes (VENUS-δf,
NEO-MC), the drift kinetic equation solver (DKES), and a
fieldline integration technique (NEO-2) have been applied
for the standard configurations of LHD (classical stellarator),
NCSX (quasi-axisymmetric) and W7-X (minimized bootstrap
current). Very reasonable agreement of these codes for
the three configurations has been obtained. This work is part
of the International Collaboration on Neoclassical Transport
in Stellarators.
Consequences of Assuming Incompressible ExB Drift in
Neoclassical Transport Theory
The conventional “local ordering” assumptions made in the
theory of neoclassical stellarator transport to derive the linearized
drift kinetic equation decrease the number of variables
in the problem by two, with both the flux-surface label
and kinetic energy becoming mere parameters. To express
the resulting mono-energetic kinetic equation in conservative
form requires that the E×B drift within the flux surface
be assumed incompressible. The validity of this assumption
has been investigated by using a δf Monte Carlo code to
solve the local kinetic equation with the option of retaining
the kinetic energy as a variable. Results indicate that the
assumption of incompressible E×B drift is appropriate as
long as this drift is not large enough to compete with the
poloidal component of a particle’s drift along the field line.
When this “resonance” condition is reached, mono-energetic
solutions of the kinetic equation significantly underestimate
the resulting neoclassical transport.
Correction of Neoclassical Fluxes to Satisfy Momentum
Conservation
Following the method of Taguchi (Phys. Fluids B 4 (1982)
3638), solutions of the mono-energetic drift kinetic equation
employing the Lorentz (pitch-angle scattering) collision
operator have been corrected so that the flux surface averaged
neoclassical fluxes, determined from them satisfy parallel
momentum conservation for a multi-species plasma. As
expected from physical considerations, calculations of the
parallel electrical conductivity are strongly affected by this
momentum correction but changes in the radial particle and
energy fluxes are negligible at reactor relevant collisionalities.
The bootstrap current is significantly reduced in pure
ion-electron plasmas (by roughly a factor of two in W7-X)
but rapidly approaches its uncorrected level as the effective
charge state is increased by the introduction of impurities.
Predictive and Analysis Transport Code
Transport simulations for different W7-X magnetic configurations
and heating scenarios have been continued to extend

the reference profile database. The neoclassical transport
simulations for W7-X are based on the DKES database of
mono-energetic transport coefficients for the low-mirror, the
standard, and the high-mirror configurations with ι(a)=1.
Here, the standard configuration has the lowest neoclassical
transport which is further reduced with increasing β (whereas
the bootstrap current increases with β). The high-mirror
configuration fulfils the optimisation criterion of minimized
bootstrap current as long as “electron-root” scenarios are
avoided, although the bootstrap current is also expected to
increase with β (due to reduction of the toroidal mirror term).
The ray-tracing code TRAVIS has been included as a module
in the transport code to self-consistently simulate modifications
of electron cyclotron resonance heating (ECRH), noninductive
current drive, and plasma profiles. The upgraded
codes can now handle multi-beam heating schemes with reflection
from mirrors and the vacuum vessel which is especially
important for O2 (second harmonic of the ordinary mode)
and X3 (third harmonic of the extraordinary mode) scenarios
with incomplete first-pass absorption of the ECRH power.
Transport Simulations of High-Power O2 Heating in W7-X
ECRH at densities as high as 2×10 20 m -3 is envisaged for
W7-X at the second harmonic of the ordinary mode (O2).
First-pass absorption of O2 ECRH is relatively poor for the
projected plasma parameters, enforcing the adoption of a
multi-pass absorption scheme with a fixed launching geometry
to conform with the placement of mirrors and reflecting
surfaces within the vacuum vessel. Using the transport/raytracing
package, this scheme is predicted to deliver threepass
absorption in excess of 95 % and produce plasmas with
〈β〉≈4 % for 10 MW of ECRH power. For such simulations,
the combination of Shafranov shift and diamagnetic effect
moves the ECRH deposition zone significantly inwards
which is most easily counteracted by increasing the initial
strength of B by several percent.
ITER Benchmark of the Ray-Tracing Code TRAVIS
A successful benchmark with the reference scenario 2 for
ITER has been performed with the recently developed raytracing
code TRAVIS. In particular, the electron cyclotron current
drive (ECCD) was calculated for both the upper and equatorial
launcher. It has been found that for the range of angles
expected to be optimal for ECCD, accounting for momentum
conservation is mandatory. Additionally, the scenario with
reduced magnetic field has been considered, where it was
found that the ECCD efficiency (as well as the deposition profile)
may be significantly altered for the equatorial launcher
due to unwanted absorption at the higher (parasitic) harmonics.
Divertor Transport Studies for Helical Devices
Transport essentials of the helical divertor in LHD were
investigated and compared to those already intensively studied
Theoretical Plasma Physics
88
for the island divertor of W7-AS, aiming at identifying common
physics issues of two helical devices with completely
different divertor concepts and geometries. For W7-X, a
systematic numerical study of the island screening effect on
recycling neutrals and intrinsic impurities has been started
with the standard island divertor configuration; preliminary
results are being analyzed. The EMC3-EIRENE code is
being implemented for NCSX.
Configuration Studies for W7-X
The configuration space of Wendelstein 7-X has been explored
at large toroidal mirror ratios. These configurations
show worsened interchange stability properties as both
shear and depth of the vacuum magnetic well are reduced so
that most configurations become interchange unstable at
medium to high β values. Another interesting quality is a
further reduction of the parallel current density which completely
suppresses the dipole component of the Pfirsch-
Schlüter currents for mirror fields around 30 %. Configurations
with negligible Shafranov shift at 〈β〉≈10 % can
be found.
Recovery of External Coil Currents for W7-X Vacuum
Configurations
The fast equilibrium reconstruction technique, called function
parametrisation (FP), was applied, indirectly, to recover
the external coil currents of W7-X in an inverse transformation.
The “inversion” is in the mapping of (known or
pre-determined) physical parameters of a configuration
onto the coil currents. The importance of this lies in the
fact that it serves to answer queries on the feasibility of
desired configurations with respect to allowed values of
external currents, something very crucial during the operation
of stellarators. The method employs an iterative minimisation
of target functions using the FP with the coil currents
as independent parameters since direct inversion is
not possible.
Scientific Staff
C. D. Beidler, M. Borchardt, S. Braun, M. Drevlak, D. Eremin,
Y. Feng, J. Geiger; P. Helander, K. Kauffmann, R. Kleiber,
A. Könies, H. Maaßberg, N. Marushchenko, A. Mishchenko,
C. Nührenberg, J. Nührenberg, J. Riemann, A. Runov, F. Sardei,
A. Sengupta, Yu. Turkin, P. Xanthopoulos, X. Zha.
Guests
J. Canic (ORNL), T. Fülöp (TU Chalmers Göteborg),
L. Guazzotto (MIT), M. Kobayashi (NIFS), L. Koziol (USC),
R. Maingi (ORNL), M. Mikhailov (Kurchatov Institute),
D. Mikkelsen (PPPL), A. Simakov (LANL), Z. Unterberg
(DIII-D).

Max Planck Junior Research Group
“Turbulence in Magnetized Plasmas”
Head: Dr. Wolf-Christian Müller
Turbulent Convection
Turbulence driven by thermal fluctuations around a mean
temperature gradient plays a role in various physical systems
like the Sun, the earth’s atmosphere, and fusion plasmas.
Large scale direct numerical simulations of turbulent convection
in plasmas as well as neutral fluids described in the Boussinesq
approximation were performed using a parallel pseudospectral
code in fully periodic geometry. Two dimensional magnetohydrodynamic
(MHD) convective turbulence shows self-excited
quasi-oscillations between regimes that are either dominated by
buoyancy or by inertial forces depending on the mutual alignment
between velocity and magnetic field. In addition, a simulation of
a three-dimensional hydrodynamic system with 20483 collocation
points has been started, making this simulation the largest
numerical effort in turbulent convection world-wide. To this end,
the numerical code has been highly optimized for the HLRBII
supercomputer at the Leibniz computing centre in Garching.
Lagrangian Statistics of Turbulence
Turbulent transport is a key feature of many physical problems
such as plasma confinement in fusion devices, the turbulent
dynamo, or the propagation of cosmic rays in the interstellar
medium. The diffusive characteristics of turbulence are best
studied from the Lagrangian viewpoint. Lagrangian statistics
of incompressible magnetohydrodynamic turbulence are obtained
by tracking tracer particles in direct numerical simulations.
A full parallelization of the particle tracking scheme has
made it possible to use up to 1024 parallel processes. In MHD
turbulence under the influence of a mean magnetic field turbulent
diffusion and relative dispersion of the tracer particles
has been found to be enhanced in the direction of the mean
magnetic field. The results agree with the picture which has
been developed for macroscopically isotropic MHD turbulence.
Turbulent flows are commonly driven by temperature gradients.
Therefore, Lagrangian tracers have been added to the
large HLRBII-run of convective Navier-Stokes turbulence.
Compressible Turbulence
Within the Cluster of Excellence “Origin and Structure of the
Universe” the efforts to study supersonic turbulence focus on
turbulent dynamics which are probably of importance for starand
structure-formation in the interstellar medium. To this end,
a new numerical framework is being developed to work reliably
on turbulent configurations with Mach numbers greater than
five. Special attention is paid to a low dissipation approach since
thin and sharply resolved shock fronts are a dominant feature
of supersonic turbulence. The new 2D and 3D compressible
MHD codes are able to capture shocks while maintaining the
divergence free constraint on the magnetic field. The underlying
Theoretical Plasma Physics
89
numerical scheme of Kurganov-Tadmor type in combination
with third order CWENO reconstruction is built on central differences
meeting the requirements of low numerical dissipation and
of high precision. The code has been successfully tested for accuracy
and for its shock capturing ability and is currently being parallelized.
The project represents a direct point of contact with astrophysics
groups of the MPA (Hillebrandt) and LMU (Burkert).
Structure Formation in MHD Turbulence
Magnetic helicity quantifies various structural aspects of a
magnetic field. It is important in reversed-field-pinch experiments
as well as in astrophysical plasmas since its dynamics
is believed to be the cause of large scale magnetic structures
accompanying many celestial bodies. We study the associated
inverse cascade, i.e., the self-similar spectral transport from
small scales to large scales by means of direct numerical simulations
of 3D MHD turbulence. Systems with small scale drive
of turbulence and magnetic helicity have been set up resulting
in a clearly established cascade process whose characteristics
are in contradiction to all known theories. Current studies
focus on a more realistic representation of the small scale
dynamics of turbulence to verify this finding. In a complementary
activity, the behaviour of magnetic helicity in decaying
3D MHD turbulence is investigated numerically.
Fundamental Properties of Turbulence
The investigation of anisotropic cascade dynamics in MHD turbulence
permeated by a strong mean magnetic field is continued.
Recent numerical experiments as well as detailed diagnostics
of large scale simulations have led to serious doubts about the
validity of the well-accepted Goldreich-Sridhar picture of anisotropic
turbulence. Further efforts will be necessary to corroborate
this claim. Numerical investigations of the monoscaling property
of probability density functions (PDFs), recently found in the
solar wind, show that this feature is probably a new universal
symmetry of turbulence. We found it in various turbulent MHD
and Navier-Stokes systems for the two-point energy fluctuations.
The PDFs resemble Levy laws of gamma-type ~1/x 1+k exp(-x/x 0 ),
k>0. A newly developed theory in the spirit of polymer fragmentation
models explains the observed behaviour as a consequence
of a turbulent transfer process in spectral space and restricts the
monoscaling property to cascading quantities like energy or density
(in the compressible case). Triad interactions, the fundamental
building blocks of non-linear dynamics in incompressible turbulence,
are studied in 3D Navier-Stokes and MHD-turbulence. After
the necessary diagnostic tool has been developed and successfully
tested on the dual cascade of 2D hydrodynamic turbulence,
the analysis is currently being extended into the third dimension.
Scientific Staff
A. Busse, T. Hertkorn, S. Malapaka, M. Momeni, D. Škandera,
Y. Rammah, Ch. Vogel.

Helmholtz University Research Group
“Theory and Ab Initio Simulation of Plasma Turbulence”
Head: Prof. Dr. Frank Jenko
The main goal of this project (in collaboration with the
Institute for Theoretical Physics at the University of Münster)
is to treat the important unsolved problem of plasma turbulence
in an interdisciplinary way. To this end, we extend and
extend ideas from fluid turbulence, non-linear dynamics, and
statistical physics. Spanning a wide range of approaches,
from simple analytical models to simulations on massively
parallel computers, we strive for a deeper understanding of
the fundamental processes in turbulent magnetoplasmas.
Beyond this, we hope that this project helps to improve the
general dialogue and cross fertilization between plasma
physics and the related fields.
Massively Parallel Gyrokinetic Simulations
The non-linear gyrokinetic continuum code GENE has been
developed during past years. It includes the following effects:
(1) fully kinetic ions and electrons [passing and trapped]
(2) beam ion and impurity species [passive and active]
(3) collisional scattering in pitch angle and energy
(4) electromagnetic effects
(5) general toroidal geometry or simple model equilibria.
Moreover, GENE runs on several parallel platforms and has
been shown to scale almost linearly up to 32,768 processors
on an IBM BlueGene architecture. It is thus suited for high
resolution runs containing most of the physics which is currently
considered important for turbulence and transport in
the core of magnetized fusion plasmas.
Non-linear Saturation of Trapped Electron Modes
While it has been known for many years that ion temperature
gradient (ITG) modes are usually saturated via the nonlinear
generation of zonal flows, we have found a different
behaviour for trapped electron modes – another key driver
of tokamak core turbulence. Recently, several research
groups in the US have confirmed this result. Via non-linear
GENE simulations and careful postprocessing of the simulation
data we have found that the turbulent E×B fluctuations
induce a perpendicular scattering of the particles which may
be described by an additional diffusion term in the basic
equations. Thus, the long wavelength modes causing most
of the transport are damped by small scale vortices. This
explains the similarity of non-linear and linear modes in the
low wavenumber regime. Moreover, we can now construct
refined quasi-linear transport models which describe the
non-linear runs quite well.
Turbulent Transport of Fast Ions
Studies on the interactions of fast ions in the plasma with the
background turbulence were carried out employing both
Theoretical Plasma Physics
90
simple two dimensional models of passive tracers in turbulent
or pseudo-turbulent fields as well as direct three dimensional
simulations with the GENE code. We were able to
show that under certain, rather generic conditions, the diffusivities
of particles up to about 10 times the thermal energy of
the plasma resemble those of the main ions. The underlying
physical mechanisms was identified and explained. This
finding may serve as an explanation of the relative inefficiency
of neutral beam current drive observed in ASDEX
Upgrade under certain conditions.
Turbulence and Transport in the Core of Stellarators
We also conducted GENE simulations of adiabatic ITG turbulence
in the stellarators Wendelstein 7-X and NCSX.
For Wendelstein 7-X, we found that there exist several fundamental
features different from a tokamak, including the
role of zonal flows for turbulence saturation, the resulting
flux-gradient relationship, and the co-existence of ITG
modes with trapped ion modes in the saturated state. The
resulting transport levels are very moderate, indicating low
ion temperature profile stiffness.
In the case of NCSX, we found that zonal flows are not
responsible for the saturation level, and that the normalized
(with respect to the minor radius) ion temperature gradient
for ITG instability is relatively large compared to a tokamak.
The transport levels are again quite moderate. Further
studies along these lines, also for non-adiabatic ITG modes
and trapped electron modes, are currently underway.
Magnetohydrodynamic Dynamos in Spherical Geometry
Employing the non-linear MHD code DYNAMO, we investigated
the effect of turbulent fluctuations on the onset of
dynamo action in spherical geometry. These studies are
closely linked to the present generation of liquid sodium
experiments like the one at the University of Madison at
Wisconsin. For the first time, it could be shown that certain
findings from recent 3D periodic box simulations carry over
to finite size systems. This concerns, in particular, the rise
and saturation of the critical magnetic Reynolds number
with the fluid Reynolds number. However, there are indications
that the underlying mechanisms are different in the
two situations. Detailed analyses of simulation data are supposed
to shed light on these questions and are expected to
indicate ways of lowering the critical magnetic Reynolds
number in actual experiments.
Scientific Staff
T. Görler, T. Hauff, F. Jenko, F. Merz, M. Püschel, K. Reuter.

Helmholtz Junior Research Group
“Computational Material Science”
Head: Dr. Ralf Schneider
The group studies effects on materials in contact with fusion
and low-temperature plasmas. The major objective is the
development and application of computational physics tools.
Development of a Multi-scale Model for the Interaction of
Hydrogen with Graphite
The multi-scale model was extended further by including the
formation and destruction of hydrogen molecules and the chemical
reactions between hydrocarbons and hydrogen (Küppers-
Hopf cycle). The model has been applied to study hydrogen
retention and release from deposits collected from the leading
edge of the neutralizer of Tore Supra. The simulations showed
that the macropores play the dominant role in the retention and
release behavior of hydrogen. The hydrogen released from
the micropores and mesopores is adsorbed on the surfaces of
the macropores. This internal deposition of hydrogen increases
the tritium retention problem for carbon in a fusion reactor.
Atomistic Description of the Plasma-wall Interaction using Ab
Initio Methods
Highly accurate global potential energy surfaces for C2H +
3 and
C2H +
5 were generated using cluster expansions. They agree
well with spectroscopic frequencies within several cm-1 .
Density Functional Theory methods were applied to study
the diffusion of atomic hydrogen trapped within crystalline
graphite. The ab initio molecular dynamics calculations at
10 K and 300 K show that the H atom forms a chemical bond
with one of the C atoms in graphite. At these temperatures
the H atom is not able to overcome the barrier and thus is
not able to diffuse. These results drastically differ from
those obtained by the use of the empirical Brenner potential
where the H atom is able to diffuse freely. The potential
energy curves calculated using the Brenner potential show a
flat potential in the central region between graphite planes
whereas for DFT calculations a higher potential energy
region between the two planes is observed due to the contribution
from the non-local pseudo-potential energy term.
Kinetic Modelling of Complex Plasmas
Kinetic modelling of plasmas with PIC (Particle-in-Cell)
methods was done in close collaborations with experiments
at the Ernst-Moritz-Arndt University in Greifswald within
the Transregio TR-24 project. Calculation of spatial-temporal
emission profiles in RF-discharges in oxygen including
the formation of negative ions and comparison with experiments
allowed for an estimate of the heavy ion collision
cross-section for dissociative excitation of atomic oxygen
+ by energetic O2 . The oxygen molecular ions get their maximum
energy at the electrode after crossing the sheath.
Theoretical Plasma Physics
91
Figure 4: Distribution of the plasma potential in an azimuthal segment for
quasi steady-state in SPT-100. The fluctuations are clearly visible.
PIC-modelling of electric propulsion Hall thrusters (SPT-100)
demonstrated the importance of secondary electron emission
for the operation of this system: electrons emitted from
the surface of the SPT-100 have lower energies than the
impinging ones. They leave the walls on a different spiral
trajectory which is displaced towards the anode. This creates
a high density low energy layer close to the walls which
increases the electron conductivity strongly in this region.
Another reason for electron cross field transport and axial
currents beyond classical estimates are azimuthal fluctuations,
which were visible in the simulations.
Figure 5: Time evolution of the azimuthal profile of the plasma potential in
the center of the discharge channel. The propagation of the fluctuations
can be seen.
Scientific Staff
K. Matyash, A. Rai, R. Schneider, A.R. Sharma, F. Taccogna.

EURYI Research Group “Zonal Flows”
Head: Priv.-Doz. Dr. Klaus Hallatschek
The project started towards the end of 2007 with the employment
of two doctoral students in November.
The targets for the first year (2008) are a theoretical understanding
of the experimental GAM frequencies and the turbulent
control of the scale length of the zonal flows.
Geodesic Acoustic Mode Studies: Impact of Coupling to Sound
Waves and Turbulence Effect
Analogous to the well known zonal winds in the atmosphere
of gas planets, plasma zonal flows (ZF) are excited
due to the quasi-2D restriction of the turbulence perpendicular
to the magnetic field. Different from the purely 2D
planetary zonal winds, the inhomogeneous magnetic fields
frozen into the moving plasma excite strong flows parallel to
the field as the circulating flux ropes compress or expand to
adjust to the ambient conditions. Depending on the magnetic
geometry, the parallel flow may have the effect of a changed
effective inertia (typically in the tokamak core where the
safety factor is around one) or can be such a strong energy
drain that a stationary flow pattern becomes impossible and
an oscillation between plasma compression and flow results
(usually in the tokamak edge with q~3-5), the Geodesic
Acoustic Mode (GAM). Stationary ZFs and GAMs have
turned out to be a ubiquitous phenomenon in many magnetic
confinement devices (AUG, CHS, H-1, HL-2A, JFT-2M,
Jet, JIPP-T2, Textor, TJ-2, T-10). The increasing detail of
the available measurement data on the GAMs allows for a
quantitative comparison with theoretical concepts of the
plasma flows.
In particular, the GAM frequencies in ASDEX Upgrade discharges
with circular flux surfaces1 agreed for low gradients
with the theoretical GAM frequency ωcirc = cs /R, with
κ=5/3 and cs = (see figure 6). However for GAMs at
higher gradients the experimental frequencies were up to a
factor two higher and for elliptic discharges up to a factor
two lower than that.
The down shift of the GAM frequency (neglecting the coupling
to sound waves) for elliptic Miller geometry3 including the
differential Shafranov shift was computed analytically2 2κ
2T/ mi
.
Just using the reconstructed shape of the flux surfaces resulted
in a frequency still about 30 % too high. Including the very
strong differential ellipticity for the respective discharges is
1 th G. D. Conway et al., 34 EPS Conf. on Control. Fusion and Plasma Physics
(Warsaw, Poland) paper O4.009 (2007); Conway et al.: “Geodesic acoustic
mode scaling and core localization in ASDEX Upgrade using Doppler
reflectometry”, Plasma Physics and Controlled Fusion, to be published.
2 K. Hallatschek: “Nonlinear three-dimensional flows in magnetized plasmas”,
Plasma Physics and Controlled Fusion 49, B137-B148 (2007).
3 R. L. Miller et al.: Physics of Plasmas 5, 973 (1998).
Theoretical Plasma Physics
92
enough to match theoretical and experimental frequencies.
However, the large uncertainties of the reconstruction in the
edge-region require a more detailed survey of data to be
satisfactory.
To facilitate extensive comparisons including the shaping
effects, which are planned for next year, an eigenvalue code
for the computation of GAM frequencies in arbitrary Miller
geometry, including the coupling to parallel sound waves
was written. It turned out, that the presence of the sound
waves typically shifts the GAM frequency by about 20 % –
not enough to be relevant at the current detail level. The
code also yields the hypothesized windows of GAM activity
due to resonances with the sound waves, but will require
accurate flux surface data for a meaningful validation with
the experiment.
The problem of the excess frequencies in case of high gradient
discharges is most likely caused by the turbulence itself. For
once it is possible that the turbulence simply increases the
GAM frequency due to its non-linear interaction 2 . On the
other hand, due to the rapid changes of the plasma parameters
throughout the region with GAM activity, the turbulence
might synchronize the GAM frequency to an area of relatively
high temperature, i.e., high frequency.
Figure 6: From [2]. Measured GAM frequencies (points), and calculated
linear GAM frequencies including sound wave coupling, using a Miller [3]
equilibrium reproducing the parameters R, r, R’, k, k’ of the nominal equilibrium.
Experimental data from [1].
Scientific Staff
N. Gürtler, R. Hager.

Supercomputing and other
Research Fields

Introduction
The Rechenzentrum Garching
(RZG) traditionally provides supercomputing
power and archival
services for the IPP and other
Max Planck Institutes throughout
Germany. Besides operation
of the systems, application support
is given to Max Planck Institutes
with high-end computing
needs in fusion research, materials science, astrophysics,
and other fields. Large amounts of experimental data from
the fusion devices of the IPP, satellite data of the MPI for
Extraterrestrial Physics (MPE) at the Garching site, and data
from supercomputer simulations are administered and stored
with high lifetimes. In addition, the RZG provides network
and standard services for the IPP and part of the other MPIs
at the Garching site. The experimental data acquisition software
development group XDV for both the W7-X fusion
experiment and the current ASDEX Upgrade fusion experiment
operates as part of the RZG.
Furthermore, the RZG is engaged in several large projects in
collaboration with other, partly international scientific institutions.
One of these projects is a bioinformatics project
dealing with genome research, another one the ATLAS project,
which is part of the LHC experiment at CERN. And finally,
the RZG is a member of DEISA, a consortium of the leading
European supercomputing centers supporting the advancements
of computational sciences in Europe. In this project the
RZG holds the task leaderships for global file systems, for the
operation of the distributed infrastructure, for applications
enabling, and for joint research activities in plasma physics and
in materials science. All these projects are based on new software
technologies, among others so-called Grid-Middleware
tools. Since the importance of Grid technology for international
collaborations has significantly increased in recent years,
broad competence has to be established also in this field.
Major Hardware Changes
The supercomputer landscape, consisting of the IBM pSeries
690 based supercomputer and the IBM p575 based cluster of
8-way nodes, has been augmented in September 2007 with an
IBM BlueGene/P system with 8,192 PowerPC@850MHz-based
cores which is especially suited for applications scaling up to
1,024 cores and beyond. Furthermore, a series of Linux clusters
with Intel Xeon and AMD Opteron processors is operated,
which has been further extended in the area of Intel Xeon quadcore
and AMD dual-core Opteron based Linux clusters. Besides
the generally available systems, dedicated compute servers
are operated and maintained for: IPP, Fritz-Haber-Institute, MPI
for Astrophysics, MPI for Polymer Research, MPI for Quantum
Computer Center Garching
Head: Dipl.-Inf. Stefan Heinzel
A major task has been the optimization of complex
applications from plasma physics, materials
science and other disciplines. The data acquisition
system of W7-X has been implemented
on a smaller existing device (WEGA) and reaches
its test phase. For the FP6 EU project DEISA,
codes from Plasma Physics (GENE and ORB5)
have been enabled for hyperscaling to make
efficient use of up to 32,000 processors.
95
Developments for High-End Computing
Optics, MPI for Extraterrestrial
Physics, MPI for Biochemistry,
MPI for Chemical Physics of
Solids, MPI for Physics and MPI
for Astronomy. In the mass storage
area, the capacity of the new automated
tape library Sun SL8500
has been extended to 6 PB of
compressed data. Both LTO3 and
LTO2 tape drives are supported.
The application group of the RZG gives support in the field of
high-performance computing. This includes supervising the
start-up of new parallel codes, giving advice in case of software
and performance problems as well as providing development
software for the different platforms. One of the major
tasks, however, is the optimization of complex codes from
plasma physics, materials sciences and other disciplines on the
respective, in general parallel high-performance target architecture.
This requires a deep understanding and algorithmic
knowledge and is usually done in close collaboration with
the authors from the respective disciplines. In what follows
selected optimization projects are presented in more detail.
GEM Code
The GEM (Gyrofluid-ElectroMagnetic) code from the IPP
plasma theory solves nonlinear gyrofluid equations for electrons
and one or more ion species in tokamak geometry. It is
restricted to a local approach in geometry, a so-called fluxtube
approach. According to the parallelization concept of
one-dimensional domain decomposition along the magnetic
field the maximum number of processors to be used was 16.
The new code version GEMR treats the full geometry in the
radial x-direction. Hence, more realistic simulations of turbulence
in experiments like JET and ITER are now in progress.
However, the necessary grid resolution of at least 1024×512×16
is already far too large to be run on just 16 processors.
Correspondingly, the scaling properties of the GEMR code
had to be improved towards many hundreds of processors.
After the single-processor performance had been increased
by 50 %, the parallelization concept was expanded to a twodimensional
domain decomposition by additionally parallelizing
along the x-coordinate. For this purpose the index structure
of the most important arrays had to be adapted to avoid
unnecessary copying in connection with communication. The
parallelization of the matrix solver in x-direction was a nontrivial
task which could finally be solved with an elaborated
parallel transpose of the data and corresponding matrices.
As a result, the scalability could be increased by the envisaged
factor of 32; a parallel efficiency of 89 % from 64 to 512
processors could be observed. Hence, both the distributed

memory and compute power of 512 IBM Power 4 processors
of the “Regatta” high-performance computer at RZG
can be used now to perform simulations of JET and ITER
configurations with the GEMR code.
GENE Code
The GENE code from the IPP plasma theory is a so-called
continuum or Vlasov code for turbulence simulations. Nonlinear
gyrokinetic equations are solved on a fixed grid in fivedimensional
phase space. All differential operators in phase
space are discretised by fourth-order (compact) finite differences.
GENE can deal with arbitrary toroidal geometry (tokamaks
or stellarators) and retains full ion/electron dynamics as
well as magnetic field fluctuations. At present, GENE is the
only plasma turbulence code in Europe with such capabilities.
The version 10 of the GENE code, which was already a parallel
hybrid code using both OpenMP (for usage within an SMP) and
MPI (for usage across SMP nodes), was further enhanced by
adding new functionality and parallelizing additionally with
respect to the parallel velocity by applying domain decomposition
techniques. The new version 11 is now scaling up to
several thousands of processors. Tests on an IBM BlueGene/L
at IBM Watson Research Center showed quasi-linear strong
scaling from 1,024 up to 16,384 processors (see figure 1). A
parallel efficiency of 99 % on 32,768 processors for the case
of weak scaling clearly demonstrates the capability of the
newest GENE version for efficient usage on between 10 4 and
10 5 processors of a scalable supercomputing architecture.
speedup
16
14
12
10
8
6
4
2
0
0 5000 10000 15000 20000
number of processors
ORB5 Code
The particle-in-cell code ORB5 from the IPP plasma theory
is able to simulate plasmas of high complexity and has high
relevance for ITER. Special effort was given to the ORB5
code to enable it to run with high scalability on thousands of
processors. Benchmarks showed good strong scaling properties
for different test cases up to 8192 processors and a
parallel efficiency of 88 % on an IBM BlueGene/L at the
IBM Watson Research Center.
Computer Center Garching
96
Massive Data Visualization
Since the beginning of 2006, the RZG engages in the visualization
of large datasets as typically produced by scientific
simulation programs. A dedicated visualization workstation is
used, which was purchased by the MPI for Astrophysics. On
this machine a so-called particle-cloud algorithm was implemented
and successfully applied to the massive output of the
millennium simulation by Volker Springel from the MPA. A
special feature of the program in combination with the fast
machine is that the user can interactively fly through the dataset.
Based on this experience a similar method has been implemented
to visualize plasma flux with datasets produced by the
GENE code from the turbulence group of the IPP plasma theory.
As the visualization method is independent of the geometry,
it is applicable to datasets of both tokamaks and stellarators.
In close cooperation with M. Püschel, a Java program
has been developed that allows to interactively view a complete
rendering of the plasma (half-) torus or part of the stellarator.
This has been achieved using a hardware-accelerated
point-based plasma rendering. Over 20 Million points can be
handled interactively on the visualization workstation. As the
geometry of the simulated plasma does not change, it was
possible to animate the plasma turbulence; moreover, the
physicist can interactively change the viewpoint and alter the
point size together with a brightness value. Thus different
structures in the dataset can be enhanced (see figure 2).
Figure 1: Strong scaling of GENEv11 for a small problem size (300-500 GB)
on a BlueGene/L machine at IBM Watson Research Center (measurements
in co-processor mode) Figure 2: Snapshot of the visualization program developed for the GENE
code showing a quarter of a half-torus from a tokamak dataset and some
elements to control viewpoint and presentation parameters
The Munich-ATLAS-Tier2 project
Collaborating research groups from the Max Planck
Institute of Physics (MPP) and from the Ludwig Maximilian
University (LMU) play a significant role in the ATLAS project
of the Large-Hadron-Collider (LHC) experiment at the
international European Centre for Particle Physics (Cern).

ATLAS is one particular detector, which will provide huge
amounts of data from 2008 on, and many institutes all over
the world consider working with these data. In order to make
this feasible, a hierarchical network of so-called Tier centres
has been established, by which the data is shared and replicated
in a reasonable fashion and the workload is distributed
to the centres.
In Munich, a Tier2 centre was set up by the MPP, the Physics
department of the LMU and the associated computing centres
LRZ and RZG. The tasks of a Tier2 centre are to provide a
certain amount of compute and memory resources, which are
placed at the disposal of all sites taking part in the WLCG
(world-wide LHC Computing Grid) community, and to establish
sufficient memory bandwidth and services for the data
exchange with the associated Tier1 centre. Furthermore, the
Tier2 centre has to provide and support a so-called Gridmiddleware
system, which enables all partners in the WLCG
to access and use the mutual resources.
Bioinformatics/Computational Biology
Within an interdisciplinary consortium joined by several
Max Planck Institutes, the RZG has established a soft and
hardware infrastructure for computational-biology applications
called MIGenAS (Max Planck Integrated Gene Analysis
System). Generally speaking, this environment allows integrated
access to all relevant software tools and biological
data which are required for comprehensive analyses of biological
systems and mediates transparent access to the underlying
computing resources operated by the RZG. With the
help of two scientific positions provided by the Max Planck
Society, the RZG hosts various bioinformatics services for
project-internal and public use, offers application support
for bioinformatics projects of the Max Planck Society, contributes
original software development and also participates
in various research projects.
Currently we are, for example, involved in a number of computationally
challenging analyses which are emerging from
so-called metagenomics projects: Thanks to the latest generation
of high-throughput sequencing technology, huge amounts
of DNA sequence data can nowadays efficiently be recovered
from all kinds of environmental samples. Comparing
such DNA sequence data with large databases of annotated
sequences allows one to assign species information to the
unknown sequences and thus gain insights into the biodiversity
of the corresponding habitat. Given the amount of
sequence data to be processed and the size of the relevant
databases to compare with, thorough optimizations of the
corresponding computations have become indispensable. To
this end, a systematic survey of existing algorithms and their
implementation in software was conducted in the context of
a Diploma thesis (H. Zimmerer) supervised jointly with
Prof. D. Huson (University of Tübingen).
Computer Center Garching
97
Concerning bioinformatics software development work has
been focused on the reimplementation and functional extension
of HaloLex, which is a software system for the central
management, integration, curation, and web-based visualization
of genomic and other related “omics” experimental
data (e.g. proteomics) for micro-organisms. The reimplementation
of HaloLex is based on modern software technology
and is being performed in close collaboration with the
original authors (Dept. Oesterhelt, MPI of Biochemistry).
Meanwhile, the system is capable of efficiently handling
data for any given micro-organism and the new web portal
(www.halolex.mpg.de) is already being used by different collaborations
in production for data curation of various genomes.
Videoconferencing (VC)
The VC infrastructure load surpassed the 2006 level. The
total conference time increased to 7152 h, that is about 30 %
plus compared to 2006. The Gatekeeper worked without
breakdowns, with some scheduled shut-downs due to power
supply work. The number of registered endpoints increased
to 350, a plus of 40 %. Conferences with presentation sharing
have become standard. The new Codian MCUs of the
DFNVC Service delivered a very reliable and high-quality
performance; about 30 % of all calls are multi-point. The
new booking system covering 28 rooms (8 VC rooms in
Garching, 6 in Greifswald, 14 non VC meeting rooms) has
been accepted throughout both sites. In 2006 there have
been 2123 bookings (the system was implemented in July
2006), in 2007 the number was 10767 equivalent to an average
1.5 bookings/room/working day. Several test and beta
installations have been done, including a new web-based
calendar and Microsoft’s Office Communicator and its coupling
to the VC standard H.323 via an MCU.
Data Networking
IPP’s data network infrastructure was planned with a
cabling structure in mind that can easily be adapted to future
technologies. The network realized is therefore based on the
concept of a “collapsed backbone”, consisting of high-level
switches at a few central locations which directly connect to
all endpoints via links based on copper or fibre – eliminating
the need of limiting switches at workgroup or story level.
With this structure we greatly improved overall network
performance (uplinks up to 10 Gigabit/s) and security and
integrity of data, because eavesdropping is almost impossible.
For logical security based on the functionality of the internet
protocol suite TCP/IP a packet filter firewall combined with
stateful inspection at the access point to the internet (a Cisco
6509 router with hardware-based firewall module) is implemented,
where all the incoming/outgoing packets are
checked against a set of blocking or granting rules.

Additionally all incoming electronic mail is scanned for
viruses and only clean and unobjectionable data (based on
known problems) will be passed to the internal network, the
rest gets quarantined. Spam mail marking is also active.
Based on a level of probability users can define and set filter
threshold values at their PC’s email client. In addition the
individual activation of “greylisting” drastically reduces the
incoming of unwanted emails.
After having successfully renovated the old building of the
computer center, a very flexible passive network structure
with fixed and hidden loose cables has been installed. The
active part of the data network is made up of a state-of-theart
high-performance switch-router Foundry MLX, where
all the supercomputer and server nodes get attached with the
highest performance available. The coupling of the new
BlueGene/P system with the storage subsystems was accomplished
with a 10-Gigabit-only Force10-E600 switch-router.
Data Acquisition and Data Bases for Plasma Fusion
Experiments
The main task of the XDV group at the computer center in
Garching is to develop the data acquisition and data storage
system for the W7-X experiment in Greifswald. This work
is done in close cooperation with the experiment control
group, the data analysis group as well as the diagnostic and
physics department.
The scheduling of the long discharges of W7X will be done by
predefining operational parameters in segments and scenarios.
Segments are valid for a certain amount of time and a scenario
is a fixed sequence of segments with a special physical background.
These segments contain very detailed but necessary
information for the hardware and software to operate the discharge.
Apart from the technical view of the segments the
experiment leader or physicist needs a more physical view to
the discharge description. Therefore an abstraction layer was
introduced that only shows physically interesting information
(high-level parameters). An executable segment will be generated
after verifying the consistency of these high-level parameters
by using a transformation function for every technical
parameter involved. The definition of the necessary structures
and interfaces is finished and by the end of 2007 some sample
implementations of transformation functions have been
available. The implementation of object life cycles, object
states and user access rights on objects is completed. The
package is used by the editors to visualize object properties
and to handle access to objects in a safe and consistent way.
By the end of 2007 the generic editor (Confix) for the structures
in the data base has reached its intended functionality.
The Confix editor works on all kind of objects in the data base
and can only safely be used by an experienced user who knows
about the structure and the object relations. The physicists
need much simpler and more specialized editors for defining
Computer Center Garching
98
configurations, segments and scenarios. The introduction of
the physics abstraction layer with the high-level parameters
is the basis for these editors and reduces the information presented
to the user considerably. At the moment two editors are
in development and first versions with basic functionality
are already available. The group configuration editor is used
to edit and define the description of components containing
several control stations (fast control stations and data acquisition
stations). It handles stations, the communication description
necessary to operate the stations as well as the
definition of the high-level parameters and the corresponding
transformation functions. The segment editor has all the features
to handle segment descriptions for components and
projects. If not specified differently all high-level parameters
are displayed in a standard way. If anything is changed, the
segments may be saved and by using the specified transformation
function, translated to the technical description used
for machine operation. Both editors use the life cycle package
to handle access rights and segment states correctly.
The implementation of the complete control and data acquisition
system of W7X on the already existing and simpler
WEGA device reaches its first milestone at the beginning of
2008. The control and data acquisition will then be replaced
by the new system. At the moment the first test runs are
accomplished and show promising results. Continuing tests
will also incorporate physicists of W7-X to show the efficiency
of the user interfaces and structures.
Initiated by the ASDEX-Upgrade CODAC (Control and Data
Acquisition) team, a new standard data acquisition station
was defined and constructed. Based on the serial optical link
(Hotlink standard) and a proprietary backplane defined locally,
several remotely available ADCs of various sample speeds
can be connected to any standard computers equipped with
PCI or Compact PCI slots. This solution allows the build-up
of data acquisition systems with a large number of channels.
Staff
A. Altbauer, G. Bacmeister, V. Bludov, G. Bronold, R. Bruckschen,
J. Daschner, K. Desinger, R. Dohmen, R. Eisert * , I. Fischer,
S. Groß * , K. Gross, C. Guggenberger, A. Hackl, C. Hanitsch,
C. Hanke, R. Hatzky, S. Heinzel, F. Hinterland, M. Kölbl,
G. Kühner * , H. Lederer, K. Lehnberger, J. Mejia, K. Näckel * ,
W. Nagel, M. Panea-Doblado, F. Paulus, A. Porter-Sborowski,
M. Rampp, J. Reetz, H. Reuter, K. Ritter, S. Sagawe * ,
R. Schmid, A. Schmidt, H. Schürmann * , J. Schuster,
U. Schwenn, T. Soddemann, R. Tišma, S. Valet * , I. Weidl.
Data Acquisition Group: T. Bluhm * , P. Heimann, C. Hennig * ,
G. Kühner * , J. Maier, Ch. Meyer, H. Riemann * , M. Zilker.
* IPP Greifswald

SERF
Euro-Asian electricity model
Coal and oil, in limited form
also gas, are traded over long
distances. On the global market
single prices exist for coal and
oil. In case of the secondary energy
carrier electricity, the situation
is different. Various independent
or only loosely coupled
markets exist.
A simple linear model of the European and Russian power system
was introduced. The model was optimised for minimal
overall costs for installation, production and transport while
varying the transportation capacities. The computed scenarios
of the Eurasian network show that transport between neighbouring
areas leads to more flexibility in power generation.
Mainly this effect can be employed for better usage of base
load processes and therefore lower energy costs and/or carbon
dioxide emissions. Some of the disadvantages of renewable
energies like wind power can be reduced. Advantages of a
stronger link over a wide area between east end west are very
dependent on conditions of standards and prices in the regions.
Traffic in the global model
One of the projects treated by the IPP energy and system studies
group is the participation on the design of a global multiregional
energy model. The goal of this model is to explore the
conditions under which fusion energy can efficiently enter into
the global energy market. This is realized by means of the
TIMES model generator which relies on an economic optimization
procedure. Presently the ETM is being revised by various
European research groups within the framework of SERF activities.
Our group takes care of the ETM transportation sector.
Recent improvements of both the software and input data used
reinforce the prospects for first sensible results. Responsible
for roughly one fourth of the global energy demand, future
Figure 1: Global energy consumption by private cars in two scenarios
Energy and System Studies
Head: Dr. Thomas Hamacher
Energy issues start to dominate global and local
politics. Climate changes and steadily rising oil
prices are subjects of political summits and
international meetings. System analysis is more
than ever asked to prepare sound answers and
present realistic outlooks to future developments.
The group for energy and system studies
is working on local and global, long and short
term issues. This mix seems best to produce
realistic long term visions.
99
transportation activities will have
substantial impact on the entire
energy system. As a first project,
the ETM transportation technology
base has been revised arriving,
at a more generic treatment
of future transportation demands.
Various scenario studies have
shown that the invention of very
efficient private cars, driven by
conventional fossil fuels, could
lead to substantial fuel savings
such that almost a stabilization of energy consumption by road
traffic, notwithstanding the heavily growing demands, could
be obtained, see Figure 1. In the near future a new treatment of
transportation habits together with an extension and improvement
of the ETM technology base will allow for a modal
split of transportation activities and, therefore, provide a more
realistic projection of future transportation energy needs.
Urban Energy Systems
Introduction
The United Nation Population Fund asks for a “revolution in
thinking” in the field of urban planning. Many cities in Asia,
Africa and Latin America are expected to double their population
over the next 30 years. Energy issues are certainly not the
only problems of these cities but certainly some of the most
pressing. Developing tools and methodologies to improve
urban energy systems is vital for a global prosperous future.
Still, the work of the IPP focuses on Europe for the beginning.
Greifswald
An urban energy system model for Greifswald was finalized.
This linear optimization model was developed with the model
generator TIMES. The model was used to analyse different scenarios
of future energy supply and demand within the city of
Greifswald. There are two different types of scenarios. One type
deals with the different possibilities to reach self-determined
objectives (e.g. a CO 2 -Cap), the other one analyses the reactions
of Greifswald’s energy system under changing economic parameters
(e.g. increasing energy source prices). Presently, a multiagent-model
of Greifswald and its economic circuit is being developed
with the software SeSAM. This model will be used to
examine the effects of different energy paths to the local economy,
which are defined with the former mentioned energy
model. The IPP further tries to initiate an active climate protection
process in Greifswald. The city council has passed a
ten point climate protection program. In several teams the
administration now deals with topics like energy efficiency,
biogas using, better conditions for cycling, energetic reconstruction
etc. In spring 2008 the first climate protection conference
of Greifswald will take place in cooperation with the IPP.

Figure 2: Basis: a business as usual scenario, CO2-Bound: step by step
reduction of CO emission of 40 %, Solar-City: usage of photovoltaic and
2
solar collector systems.
Malacky
Malacky is a small town in Slovakia close to Bratislava,
which undergoes a tremendous economic growth. The IPP
develops an energy model especially for Malacky. The main
emphasise of the model will be to describe a population
which expects to increase the per capita income in the next
two decades considerably and a landscape in which major
industries are developed on the green field.
Ungerhausen
A possibility to solve the dilemma between the limited fossil
resources and a growing global energy demand is to build
up local supply concepts. Such regional concepts are mainly
based on the conversion of solar energy, which is theoretically
available in huge amounts. The main focus of this study
is to compare two different conversion concepts of using
solar energy to satisfy the electricity and heating demand of
a model region in consideration of the efficiencies and economical
boundaries.
One concept is to use agricultural land and goods as well as
local wood potentials to produce energy in combined heat
and power processes. Here the analysis of flows of agricultural
products is important, because the energy production
competes with the production of food, e.g. milk or meat. If
the agricultural structure allows for the planting of energy
crops, energy potentials have to be estimated in a realistic
manner and crop rotations have to be followed.
The electricity production by photovoltaics is therefore a more
physical way of converting the solar radiation. The concept
of producing solar hydrogen is a possibility to generate heat
from electricity as well. Comparing both conversion concepts
shows a lot about potentials, consequences and limitations of
the substitution of fossil energy sources. Using combined heat
and power processes is the most effective way to reduce CO 2
emissions. The most efficient way of using the solar energy
is the installation of photovoltaic modules, because biomass
actually converts the solar radiation with efficiency of 1 %.
Energy and System Studies
100
ESCOBALT
The ESCOBALT project was finished in 2008. Results and
findings of the project can be found on the internet. One of
the goals, to create an energy saving network in the Baltic
Sea, was certainly reached. The Baltic Sea region is unique
in its variety for different concepts to supply energy.
Methodologies
Stochastic programming
The German electricity system is expected to undergo major
transitions in the future. Drivers of the expected change are
the political decision to phase out nuclear energy and the
confession to fulfil the Kyoto protocol. But also uncertain
factors like weather conditions or price developments have
an influence on the decision; therefore it is important to perform
risk analyses. With the help of stochastic programming
techniques, such uncertainties can be trapped to a certain
point. A stochastic linear program of the German electricity
system was developed to generate a system causing the
minimal total costs in consideration of uncertainties. The
fuel prices, the CO 2 prices and the wind supply where regarded
as stochastic elements. Within this work the influence
of wind to the existing system was analysed and the
phase out of nuclear energy as well as CO 2 reduction scenarios
were studied.
EPS
The IPP helps the European Physical Society to establish a
working group on energy issues. The goal of this working
group is to develop proposals for a sound European energy
research in the field of physics. While the EPS is here certainly
in competition with various other actors, the EPS
offers the chance to develop balanced and independent
views.
Outlook
Energy system studies will certainly become even more
important in the future. The problem remains that talking
about the future requires a very special care and adequate
methodologies. Only work which is well aware of these
methodological deficiencies will be able to make sound and
helpful future outlooks.
Scientific Staff
Group: M. Bartelt (Uni Greifswald), M. Baumann (TU Graz),
F. Botzenhart (Uni Augsburg), S. Braun (Uni Greifswald),
G. Dressler (FH Stralsund), J. Düweke, T. Hamacher,
N. Heitmann, J. Herrmann, M. Krüger (FH Wismar), P. Kurz
(Uni Greifswald), P. Mühlich.

Charged Water Clusters
Many aspects of the photoelectron
spectra of free molecules
are well understood. On the other
hand, electron spectroscopy of
liquids has only become possible
recently and is a field of rapidly
growing interest. Photoelectron
spectra of liquid water differ in a
number of respects from the mole-
cule: Features due to ionic state vibrations, a characteristic
of molecular conformational changes, are smeared out or
absent in the liquid. Ionization energies of all orbitals shift towards
lower values. The value of the vertical ionization energy
of the least strongly bound electrons in the liquid has been
measured some years ago. In our study of free water clusters,
we show how this literature value is smoothly approached
when ionization of clusters of increasing size is studied.
HOMO Energy Shift to Monomer (eV)
1.6
1.4
1.2
1.0
0.8
0.6
0.4
0.2
0.0
0.0
0.2
0.4 0.6
N-1/3 Figure 1 gives a graphical representation of the shift in photoionization
energy of water clusters. Experimentally, clusters
are produced by supersonic expansion of water vapour
into vacuum. Clusters with a rather broad size distribution
are thus produced, the mean of which can be varied by
changing the expansion conditions (pressure and nozzle
temperature). An empirical scaling law, derived from mass
spectrometry of cluster beams, was used for estimating this
mean size. The energy plotted in figure 1 is measured from
the adiabatic peak in the isolated molecule to the maximum
of the first photoelectron peak in the cluster.
The linear dependence of these energies vs. inverse size is in
line with expectation, if their main origin is the polarization
Electron Spectroscopy
Head: PD Dr. Uwe Hergenhahn
Photoelectron spectroscopy is a valuable tool
for the study of material properties, as seen for
example by its use in the investigation of fusion
reactor wall materials. In fundamental studies
of its application to materials in general we
have measured photoelectron and autoionization
spectra from free water clusters. The sizedependent
vertical ionization energies are shown
for the first time.
Cluster
Monomer
Liquid Water
0.8
1.0
Figure 1: Energy difference of the least strongly bound photoelectrons of
water clusters as a function of inverse cluster size. N is the mean value of
the number of molecules in the cluster. The asymptotic value for liquid
water is taken from the literature.
101
Autoionization of Clusters
screening of the positive hole in
the cluster. Initial state effects,
surface charging and changes
of the nuclear framework in the
ionization process are thus found
to be of minor importance. For
the latter, this is confirmed by
the fact that these shifts are
practically identical in heavy
water (D 2 O).
The influence of the chemical environment on autoionization
in weakly bonded systems has been studied recently,
and a new transition pathway, which is only possible
because of the cluster environment, identified (Intermolecular
Coulombic Decay, ICD). ICD is expected to be a
universal phenomenon, but so far has only been identified in
noble gas clusters. The presence of a large quantity of low
kinetic energy electrons coincident with primary inner
valence photoelectrons from water clusters is the first experimental
evidence for ICD in a hydrogen bridge-bonded system
(figure 2). The same set-up was used to record electronelectron
coincidence spectra of Ne clusters. Here, ICD is
well-known from our experiments using a conventional
(non-coincident) spectrometer. These earlier findings were
beautifully corroborated.
Coinc. Events /eV
Kinetic Energy (e1) (eV)
10000
8000
6000
4000
2000
0
16
14
12
10
8
6
4
ICD Spectrum
Scientific Staff
5 10 15 20
Kinetic Energy (e2) (eV)
250
S. Barth (1-3/07), V. Ulrich (1-7/07), M. Mucke (8-12/07),
M. Förstel (9-12/07), T. Lischke, A. M. Bradshaw, U. Hergenhahn.
Inner Valence
2
Coinc. Events / (eV x eV)
Photoelectron Spectrum
0 2000 4000 6000
Coinc. Events /eV
Figure 2: Intensity map of photoelectron-secondary electron pairs for inner
valence ionization of water clusters. The ionization energy was set to 45 eV.
The joint emission probability for each combination of kinetic energies of the
two electrons detected in coincidence is presented in the two-dimensional
map. Spectra shown in the top and righthand panel pertain to summation over
all secondary electron energies or all photoelectron energies, respectively.

University Contributions to
IPP Programme

In 2007 there were some retirements
of members of the Board
of Scientific Directors at IPP.
Prof. Behringer left IPP in August.
To elect his successor within a
joint appointment of Augsburg
University and IPP, a colloquium
took place at Augsburg University
on December 11 th . In consequence
of the retirement of
Prof. Fußmann, the cooperation
with the “Humboldt-Universität
zu Berlin” ended in September.
A concept for a new cooperation with the Technical University
Berlin is in progress and is expected to be signed in 2008.
Since fusion-relevant physics and engineering are not the most
prevalent subjects in Germany’s academic landscape, sparking
student’s interest in high-energy plasma physics and other
fusion-relevant fields is a duty and delight. Teaching at universities
therefore has a sound tradition at IPP. In 2007 there
were about 107 contact hours at universities or universities
of applied sciences in Germany or neighbouring countries:
Augsburg, Bayreuth, Bochum, Ghent, Greifswald, Helsinki,
Munich, Padua, Stralsund, Tübingen, Ulm and Vienna.
Lecturing at universities is supplemented by the IPP’s
“Summer University in Plasma Physics”: one week of lectures
Country Postgraduates Postdocs
male female male female
Australia 1
Austria 1
Canada 1
Chile 1
Czech Republic 1
France 1
Germany 30 9 10 1
Greece 1
India 2 1 1
Italy 3 1 1
New Zealand 1
Poland 1 1
Romania 1
Russia 1 2
Spain 1
The Netherlands 1
Ukraine 1 3
United States of America 1
Yugoslavia 1
38 14 26 3
52 29
Table 1: Countries of origin and sex of the 52 postgraduates and 29 postdocs
at IPP (31.12.2007)
Cooperation with Universities
Author: Dr. Axel Kampke
Many important goals in plasma physics and
materials science have to be met on the way to
a fusion power plant. Since this process will
last another generation, IPP attaches great importance
to the training of young scientists. The
close interaction with the universities in teaching
and research is therefore an important part
of the mission of IPP. It has also borne fruit in
recent years. Moreover, the joint projects, which
exist with several universities, form an integral
part of the IPP research programme.
105
given by IPP staff and lecturers
from partner institutes providing
detailed tuition in nuclear
fusion – in 2007 for the 22 nd
time at Greifswald.
The international character of
fusion research is also reflected
in the countries of origin of graduate
students at IPP: one fourth
of the postgraduates and more
than 60 per cent of the postdocs
are from abroad. Table 1 shows
the distribution with respect to
country and sex of the 52 postgraduates and 29 postdocs at
the end of 2007. Due to the restricted time for their work at
IPP the total numbers of supervised postgraduates and postdocs
within 2007 are higher by a factor of 1.3 than the above
mentioned numbers.
In addition, IPP uses specific instruments developed by the
Max Planck Society, the Helmholtz Association and the
Deutsche Forschungsgemeinschaft (DFG) for more intensive
networking with universities on a constitutional basis:
• participation in the DFG Collaborative Research Centre
Transregio 24, “Fundamentals of Complex Plasmas”, at
Greifswald University
• the “International Max Planck Research School on Bounded
Plasmas” at Greifswald in cooperation with Greifswald
University
• a “Helmholtz Virtual Institute” together with the Universities
of Stuttgart and Karlsruhe and Karlsruhe Research
Centre
• two “Helmholtz Young Investigators Groups” – “Computeraided
Materials Sciences”, headed by Dr. Ralf Schneider,
and “Theory and Ab Initio Simulation of Plasma Turbulence”,
headed by Dr. Frank Jenko – in cooperation with
the Universities of Greifswald and Münster, respectively,
• the “Max-Planck Young Investigators Group” “Turbulence
in Magnetised Plasmas”, headed by Dr. Wolf-Christian
Müller, and
• the “Young Investigators Group” “Zonal Flows”, headed by
last years “European Young Investigator Award” winner
Dr. Klaus Hallatschek.
The young investigators groups got founded a common 500thousand-Euro-Linux-Cluster
by the Helmholtz Association.
In 2006 IPP was successful within the “Excellence
Initiative” of the German government; the proposals for
“Munich Centre for Advanced Photonics” and “Origin and
Structure of the Universe” – both in cooperation with LMU
and TUM – were accepted as “Clusters of Excellence”. In
2007 “Origin and Structure of the Universe” was officially
established in the former “ITER building” of the IPP.

Species distribution [% n e ]
University of Augsburg
Lehrstuhl für Experimentelle Plasmaphysik
Head: Prof. Dr. Kurt Behringer
Low Temperature Hydrogen
at the NBI source. A pressure
Plasmas
variation at GLADIS showed
that increasing the pressure at
Basic investigations on diagnos-
constant RF power causes a
tics and modelling of low temperature,
low pressure plasmas
with hydrogen (or deuterium) ad-
strong increase in H
mixtures are carried out at inductively
driven RF plasmas,
microwave excited and electron cyclotron excited plasmas
covering a wide range of pressure and input power and thus,
a wide plasma parameter range. Focus is laid on molecular
plasma physics. The methods developed are applied to the
cold edge plasma of ASDEX Upgrade and to several ion
sources at the IPP.
+ The research at the University focuses on the
development and application of diagnostic
methods for low temperature plasmas, in particular
for hydrogen ion sources, and on studies
of plasma-surface interaction. The work is carried
out in close collaboration with several
divisions of the IPP.
and H + at 3
the expense of H + . From the
2
measurements of the molecular
radiation a gas temperature of
1000 K has been obtained; the
vibrational temperature could be estimated to be 5000-
8000 K for H and, as expected, lower for D : 3000-5000 K.
2 2
In order to measure the electron energy distribution function
(EEDF) directly, the Boyd-Twiddy setup has been applied to
a conventional Langmuir probe system. Since a voltage ramp
is superposed by an AC modulated signal, the current at the
modulation frequency directly yields the EEDF, whereas the
80
70
60
50
40
30
nH /n H2
20
H
10
0
0.25
0.20
0.15
0.10
0.05
0.00
DC current yields the plasma potential, the floating potential,
and the electron and ion saturation currents. In addition, an
RF disturbance is automatically filtered by a fast Fourier
transformation. Measurements carried out at the experiments
at the University show a good agreement between the conventional
Langmuir probe and the Boyd-Twiddy technique,
the latter being much less noisy. The setup has been transferred
to the high power (P=60-120 kW), RF driven, negative
hydrogen ion sources developed at IPP. EEDF’s are shown in
the ITER section of this report. Electron density profiles on
the central axis of the negative ion source BATMAN from the
plasma grid to the driver are shown in figure 2 for two grid
configurations (LAG and CEA). A low and a high bias current
(1 A and 10 A) have been applied to reduce the amount of coextracted
electrons. The electron density decreases exponentially
over 4 cm towards the grid, being drastically depleted
at 10 A for both grids. It was assumed that the position of the
magnets for the magnetic filter field (FF) determines the
sheath of electron depletion; however, the measurements
clearly show a correlation with the grid position.
+ H
3
+ H
2
+
D
nD /n D2
+
D + 2
D + GLADIS
AUG:NBI-RF source
3
0 15 20 25 30 60 70 80 90
RF power [kW]
Figure 1: Species distribution and the atomic to molecular density ratio in
two positive ion RF sources at IPP
Two RF driven positive hydrogen ion sources, one of the neutral
beam injection system (NBI) at ASDEX Upgrade and the
one of the high heat flux test facility GLADIS were investigated
by spectroscopic techniques at different RF input powers.
The NBI source at ASDEX Upgrade works at higher
powers, has a rectangular body, and worked with deuterium
during the measurements, whereas the smaller cylindrical
GLADIS source works with hydrogen at lower power levels.
The ion species distribution was determined by H α -Doppler
spectroscopy of the extracted ion beams. In addition, the radiation
of atoms and molecules in the source plasma itself was
measured to determine the density ratio of atoms to molecules.
As shown in figure 1 the ion species distribution and the atomic
to molecular density ratio depend clearly on input power.
Furthermore, the assumption that a higher RF input power
increases the degree of dissociation of the molecules and
accordingly the atomic ion fraction has been confirmed and
quantified. The difference in absolute values and ion species
distribution among the two sources is most probably due to the
different RF power and gas pressure which are both higher
Density ratio: atoms/molecules
107
Electron density [m -3 ]
5x10 17
10 17
CEA grid
LAG grid
magnets
FF
CEA
LAG
full symbols: 1A bias
open symbols: 10A bias
10
-6 -4 -2 0 2 4 6 8 10 12 14 16 18 20
Axial direction [cm]
16
Figure 2: Electron density profiles for two different grids (at low and high
bias current) of the IPP negative ion source BATMAN

Since evaporation of cesium and the formation of Cs layers
on metal surfaces play a key role in negative hydrogen ion
sources, basic investigations on Cs behaviour in hydrogen
plasmas have been started at the University in 2007. To
determine the thickness of a Cs layer, a specially designed
quartz-crystal-microbalance is used that measures the frequency
difference between two oscillating crystals. Figure 3
(inlay) shows the measured correlation between Cs evaporation
using a Cs dispenser at different currents and the
change in frequency and thus the film thickness. In contrast
to studies in high-purity conditions, the growth of Cs onto
the examined surfaces (Cu, Mo, W, steel) is inhomogeneous;
the cesium forms local, drop-like structures with a size of
several μm. SEM pictures show that only 20-30 % of the
metal is covered by those structures; consequently the measured
thickness represents an effective thickness. In addition,
a method for in-situ measurements of the work function
using the photoelectrical effect (Fowler method) has been
established. As shown in figure 3 the work function decreases
with the Cs coverage of the molybdenum surface; however
the work function does not fall below 2.8 eV towards the
expected 2.2 eV for pure Cs.
Work function [eV]
4.4
4.2
4.0
3.8
3.6
3.4
3.2
3.0
2.8
0.0
Frequency change [Hz]
600
500
400
300
200
100
Plasma Surface Interaction Studies
0
6.5A
dispenser
current
7A 7.5A
0 300 600 900 1200
Dispenser on-time [s]
0 10 20 30 40 50 60
Effective cesium thickness [nm]
Figure 3: Work function of a cesium layer on molybdenum as a function of
the effective thickness. The inlay shows the thickness of the Cs layer during
Cs evaporation using a dispenser.
In strong collaboration with the materials research group at
IPP, the ongoing work on chemical erosion of different
doped carbon materials in low pressure ICP hydrogen and
deuterium plasmas has now been focused on the one hand on
the effect of the dopant distribution, i.e. carbide grain size
and on the other hand on manufacturing and surface temperature
effects on the erosion yield (released carbon particles
per incident ion). Doping of carbon leads to a reduction of
the effective carbon surface and thus to a reduced erosion
University of Augsburg
60
50
40
30
20
10
0
Cesium thickness [nm]
108
yield in hydrogen plasmas. In-situ measurements of the fluence
resolved erosion yield were carried out by optical
emission spectroscopy (CH and C 2 band emission) in combination
with weight loss measurements and RBS measurements.
The incident ion flux towards the surface was measured
using an energy resolved mass spectrometer in combination
with a Langmuir probe. The effect of the dopant distribution
was studied with amorphous carbon layers with atomically
disperse distribution and different concentrations of the
dopant materials (V, Ti, W). Another set of these samples
was previously annealed at up to 1100 K leading to the formation
of carbide grains with a size of several nm depending
on dopant material and concentration. Figure 4 shows the
results for vanadium doped samples with a surface temperature
of 300 K and incident ion energy of 30 eV in deuterium
plasmas. The solid line represents the erosion yield of undoped
amorphous carbon. The yields show a strong decrease
with the fluence and depend strongly on the dopant concentration.
This strong reduction of the erosion yield can be
explained by a surface enrichment of the dopant material
which was proven by RBS measurements at the IPP. The
pre-annealed samples always show significantly higher
yields compared to samples without annealing; an effect
which is less pronounced for titanium doped layers due to a
less effective grain formation by annealing.
Erosion yield G C /G ion [%]
10
1
8.5%V
Scientific Staff
8.5%V
pre-annealed
1.5%V
3.5%V
Dopant: V
3.5%V
pre-annealed
a-C
1.5%V
pre-annealed
0.1
0.0 0.5 1.0 1.5 2.0
Fluence [1024 m-2 ]
Figure 4: Erosion yields of vanadium doped amorphous carbon with atomically
disperse dopant distribution and nm-sized carbide grains (preannealed)
considering different concentrations of the dopant in ICP discharges
with deuterium
U. Fantz, P. Starke, S. Dietrich, S. Briefi, J. Ebad-Allah,
D. Filimonov, S. König, A. Manhard, P. Schmidt.
Energy scenarios group: J. Herrmann, F. Botzenhart, B. Grotz,
A. Hämmerle, T. Hartmann.

Elementary reactions of
hydrogen atoms with adsorbates
and solid surfaces
University of Bayreuth
Lehrstuhl für Experimentalphysik III
Head: Prof. Dr. Jürgen Küppers
A considerable fraction of the species
impinging on the first wall of
a fusion experimental vessel are
neutrals and ions in the energy
range below a kinetic energy of about 10 eV. These particles are
not capable of causing physical sputtering, but can induce several
processes, such as chemical erosion, abstraction etc, which
contaminate the plasma. Since low-energy ions are neutralised in
the immediate vicinity of a substrate by resonance neutralisation,
it is sufficient to study low-energy atom-surface interaction.
For experimental reasons, the present work utilised only
thermal atoms with energies in the range of a few tenth of an eV.
Interaction of thermal hydrogen atoms with graphite basal
plane surface leads to the formation of weak C-H bonds on
top of C in a unique bonding scheme. The rigidness of the C
lattice in which C-H groups are embedded prevents a full
rehybridization towards strong tetrahedral sp 3 C-H bonds as
are present in alkanes. Using ultra sensitive thermal desorption
spectroscopy, we have found atomic and molecular
hydrogen release upon thermal activation between about
100 K and 700 K. First thermal (2000 K) hydrogen atoms
a
Mass spectrometer signal 10 -12 A)
0.2
0
0.6
0.4
0.2
0
D 2
D
340 K
340 K
490 K
580 K
Cooperation between IPP and the University
of Bayreuth is concentrated on investigating
fusion-relevant plasma-wall interaction processes.
Accordingly, the hydrogen atom surface
chemistry on possible reactor wall materials is
the primary research topic.
b
6
4
2
0
2
D 2
D
109
stick with a probability of about
0.1 (figure 2b) and activate the
surface towards adsorption of
further atoms in close proximity.
The total hydrogen sticking efficiency
increases up to about
0.4 and cluster of nearby C-H
groups grow very efficiently.
Figure 1 displays thermal desorption data of D coverages on
graphite from 0.00008 to 0.5 ML. Measurements with H exhibit
the same spectral features. The icons in the figure correspond to
the adsorption geometries deduced by STM. The assignment is
based on the simultaneous appearance of spectral features in
TDS after selected D exposure and is in line with measurements
of the adsorbed structures left behind on the surface after
progressive heating. The various local maxima in TDS originate
from dissociation of C-D groups in different types of adsorbed
clusters. Figure 1a displays a sequence of atomic and recombinative
molecular desorption spectra for D coverages below
0.001 ML. At the smallest D coverages only desorption of
atoms from isolated C-D groups with a maximum at 340 K is
observed. After higher D exposures (figure 1b), predominantly
pairs of C-D groups dissociate via release of D 2 , as can be
deduced from the main D 2 desorption peaks located at 490 K
(pairs with 3, 5 and 7 multiples of a cc ), and 580 K (para pairs).
340 K
490 K
340 K
450 K
580 K
0
0
200 400 600
200 400 600
200 400
Temperature (K) Temperature (K) Temperature (K)
600
c
120
80
40
0
4
2
D 2
D
265 K
500 K
540 K
580 K
450 K
520 K
Figure 1: Thermal desorption of D and D2 from the graphite basal plane after exposure to D at 150 K surface temperature (26). TD spectra were recorded with heating
rates of 1 K/s and desorbing D atoms were detected via HD formed upon collision with the chamber walls. No other desorbing species could be detected. (a) TDS
data from a surface dominated by isolated C-D groups (coverage 0.00008 to 0.001 ML, D exposures were: black 0.0008 ML, red 0.002 ML, green 0.0048 ML, blue
0.01 ML). (b) TDS data from a surface dominated by pairs (coverage 0.001 to 0.02 ML, exposures were: black 0.01 ML, red 0.02 ML, green 0.04 ML, blue 0.08 ML).
(c) TDS data from a surface dominated by big adsorbed clusters (coverage 0.02 to 0.5 ML, exposures were: black line 0.1 ML, red line 0.2 ML, green line 0.3 ML,
blue line 0.5 ML, magenta line 1.0 ML, cyan line 2.0 ML, black symbols 3.0 ML, red symbols 10 ML, green symbols 40 ML, blue symbols 100 ML).

Since D 2 desorbs at higher temperatures than D, it is immediately
clear that a C-D bond gets stronger if a neighbour C-D
group is present in a distance of an odd multiple of a cc on the
surface. Moreover, the spectra in figure 1b show that the
molecular desorption peaks are preceded by an atomic peak
at about 450 K. This shows that in a bigger cluster like a
triple, less stable and stable C-D groups exist, of which the
first dissociate via ejection of D atoms and the latter via
ejection of D 2 molecules. The occurrence of single ortho
pairs in STM coincides with the development of an additional
desorption state which is at high coverage visible as a
shoulder in TD spectra at about 540 K (figure 1c). These
ortho pairs arrange in bigger entities which do not exhibit
clearly distinguishable dissociation temperatures but lead to
desorption between 400 K and 540 K.
Also visible in TD spectra is desorption below the dissociation
temperature of isolated C-D groups. A small fraction of
atomic desorption near 200 K at low coverage (figures 1a,
1b) is seen. Approaching saturation coverage of 0.5 ML, a
pronounced molecular peak located at 265 K (figure 1c)
emerges. This shows the existence of rather unstable C-D
bonds. As stabilization of C-D pairs was only observed with
C-D group separations of odd multiples of a cc , it is suggested
that C-D groups which are separated by even multiples of
a cc from other C-D groups exhibit reduced stability and dissociate
below RT. At low coverages, only atomic desorption
from these unstable groups was observed. This can be understood
by taking into account that by ejection of a D from
such an unstable group a more stable isolated C-D group is
left behind (see the highest coverage atomic D desorption
trace in figure 1b). The mean distance between C-D groups
decreases with coverage. Accordingly, atomic desorption
below room temperature might originate from desorption of
pairs separated by large even multiples of a cc and molecular
desorption at 265 K might predominantly originate from
meta pairs, which exhibit the smallest possible separation, 2 a cc .
a
coverage (ML)
10 -2
10 -3
10 -4
10 -5
singles
b
0.2
0.1
total (D)
pairs
0
singles
10 0 0.05 0.10
-3 10-2 10-1 D exposure (ML) D exposure (ML)
University of Bayreuth
pairs
Figure 2: (a) Number of singles and pairs with respect to D exposure displayed
on logarithmic scale. The values were deduced from integration of the respective
TDS peaks shown in figure 1a, b. (b) D sticking efficiency with respect to D
exposure. The values were deduced from the D coverage data shown in a.
coverage/exposure
110
The thermal desorption data show that thermal hydrogen
atoms adsorb very efficiently on the graphite basal plane
and that C-H bonding energies can be much lower than previously
thought.
Publications
S. Wehner, P. Hoffmann, D. Schmeisser, H. R. Brand, and
J. Küppers: Influence of the substrate on the pattern formation
of a surface reaction. AIP Conference Proceedings 913,
121-126 (2007).
Conference contributions
T. Zecho, C. B. Fischer, G. Ehrenhaft, and J. Küppers:
Chemical erosion of graphite (0001) surfaces with thermal
H and D. IVC-17/ICSS-13 and ICN+T 2007, Stockholm,
Sweden, July 2007.
S. Wehner, S. Karpitschka, H. R. Brand, and J. Küppers:
Musterbildung auf nicht rekonstruierenden Metalloberflächen:
CO Oxidation auf Ir(111) und Pd(111). CRG-Workshop,
Culmitz, July 2007.
S. Wehner, P. Hoffmann, D. Schmeisser, H. R. Brand, and
J. Küppers: Pattern formation during the CO oxidation
reaction on non reconstructing platinum group metal surfaces.
X. Latin American Workshop on Nonlinear Phenomena
(LAWNP 2007), Arica (Chile), October 2007.
T. Zecho, A. Andree, C. B. Fischer, M. Le Lay, and J. Küppers:
Hydrogenation of graphite and carbon nanotube surfaces
with hydrogen atom beams. 2nd International Workshop on
Materials Science and Nano-Engineering, Awaji Island,
Osaka, Japan, December 2007.
Seminars
S. Wehner, P. Hoffmann, D. Schmeisser, H. R. Brand, and
J. Küppers: Pattern formation during the CO oxidation reaction
on non reconstructing platinum group metal surfaces.
FCFM-Seminar, Universidad de Chile, Departamento de
Fisica, Santiago (Chile), October 2007.
S. Wehner, H. R. Brand, and J. Küppers: From adsorbed molecules
to mesoscopic patterns: Experimental studies of the influence
of noise on the CO oxidation reaction on Iridium(111)
surfaces. Nonlinear dynamics: From small scales to coherent
structures (396. Wilhelm and Else Heraeus-Seminar),
Bayreuth, October 2007.
Scientific Staff
T. Zecho

Plasmagenerator PSI-2
Performing plasma diagnostic
measurements with Langmuir
probes one has to take into consideration
possible disturbances
of the plasma by the probe itself.
Apart from the probe tip, there
is especially the probe shaft that
could influence the results of a
measurement. To resolve this question, measurements were
made of the electron temperature and density using two
Langmuir probes. The probes were arranged in two positions:
In the first case, they were aligned in azimuthal direction
of the PSI-2 plasma column. In the second case, they
were placed in the same axial plane but tilted to each other
in azimuthal direction. Data was acquired keeping one
probe at fixed position while the second one was scanning
the plasma radially. We have found that, irrespective of the
geometry, the electron temperature is not affected by the
probe, however the electron density is. This result can be
explained within a theoretical transport model in which the
probe shaft acts as an additional particle sink (figure 1). It is
interesting to note that the disturbance of the plasma by the
probe takes place on a global scale.
n e and T e [normalized]
1.1
1
0.9
0.8
0.7
T
e
n
e
Model
The flow behaviour of plasmas in contact with a target surface
was investigated. The ion velocity distribution function (ivdf)
of Ar + ions was measured at different displacements from
the target using LIF techniques (see Annual Report 2006).
In addition to the ivdf, the electron temperature was measured
by means of a Langmuir probe. Assuming T e =T i and combining
the results from the ivdf and Langmuir probe measurements
the Mach number M=u/c s was evaluated (u streaming
velocity, c s =[(T e +T i )/m i ] 1/2 speed of sound). Figure 2 shows M
and the electron density at different axial positions z (spatial resolution
Δz~0.5 mm). Close to the target (z=0) the Mach number
approaches unity in agreement with the prediction by Bohm.
Humboldt-University of Berlin
Arbeitsgruppe Plasmaphysik
Head: Prof. Dr. Gerd Fußmann
-40 -20 0 20 40
Radial Position x [mm] of Disturbing Probe
Figure 1: Normalized electron density (red) and temperature (blue) measured
at fixed position while a second probe was radially driven. The calculated
density distribution is plotted in black.
The plasma physics group at the Humboldt
University operates the plasma generator PSI-2
and the electron beam ion trap (EBIT). Research
activities comprise basic plasma physics, plasmamaterial
interactions and highly charged ion
processes relevant to fusion experiments. Further
effort is dedicated to the study of plasmoids produced
on water surfaces at atmospheric pressure.
111
Our measurement is thus the
first confirmation of Bohm’s
criterion for conditions relevant
to fusion experiments. An unexpected
result is the short distance
(Δz~5 mm) over which the
final acceleration of the ions to
M=1 takes place. Using a theoretical
presheath model the measured
profiles can be reproduced
by relying on D=20 m 2 s -1 for the perpendicular diffusion coefficient.
However, this D value is unrealistically large to explain
the profiles solely by diffusion. A more refined analysis of our
results suggests that radial electric fields build up in front of the
target causing strong particle transport onto the target surface.
M LIF
M
n LIF
n
-50 -40 -30 -20 -10 0 0
z [mm]
Figure 2: Mach number and electron density as a function of axial position
Electron Beam Ion Trap (EBIT)
To complement earlier work on the line emission from highly
charged tungsten ions (see Annual Reports 1999 and 2000),
x-ray spectra from Si-like W 60+ to Ne-like W 64+ were measured
in the 1-2 Å wavelength region. Our study includes the directly
excited L-shell spectra as well as the associated satellite
emission originating from dielectronically excited W ions.
Precise knowledge of such data is essential owing to the increasing
use of tungsten as wall material in nuclear fusion
devices. The tungsten ions in the EBIT were produced by
directing a continuous flow of W(CO) 6 gas towards the trap
and ionizing the injected carbonyl compound by the monoenergetic
electron beam. Spectra were obtained for a number
of beam energies between 10 and 20 keV and analyzed
using high resolution x-ray spectroscopy. As an example, in figure
3(a) we present a 15 keV electron beam energy spectrum
showing lines from W 60+ to W 64+ recorded between 1.18 and
1.57 Å. To support our identification of the lines, wavelengths
and intensities were calculated for the ions under investigation
using an atomic structure computer package combined
with a collisional-radiative model (in cooperation with
the division Tokamak Edge and Divertor Physics in Garching).
n 0
M 0
1
0.8
0.6
0.4
0.2
M or n/n 0

Intensity [cph]
I [10-16 3
Ph/s cm /Å]
cs [10 -20 cm 2 ]
100
50
0
5
0
a)
3p - 2s
10 W 64+
5
4
3
2
1
0
b) W 63+
W 62+
W 64+
The results (figure 3b) show that atomic structure calculations
can reproduce the general pattern of the observed spectra.
The predictions for the wavelengths agree with the experimental
values to within about 2-3 %.
In a further experiment, measurements were made of the LMn
(n=3-6) dielectronic-recombination (DR) resonances using a
scanning technique described earlier (see Annual Report 1997).
The DR process proceeds by capture of a free electron to a target
ion forming an autoionizing doubly excited state followed
by a stabilizing photon emission. Figure 3c shows the DR
spectrum for the LMM resonance of tungsten ions with charge
q

Introduction
In ASDEX Upgrade thermographic
measurements are used
to monitor the surface temperature
of in-vessel components
during plasma discharges. The
heat flux to the components is
calculated from the measured
temperature evolution. Carbon
fibre composite (CFC), often used
as target material, has a substructure in the ten micrometer
range which causes a non-uniform temperature distribution
even for a homogeneous heat load. This can be observed by
measurements with a resolution in the dimension of the single
fibers, as shown in figure 1. Some isolated spots reach much
higher temperatures than the remainder, which are not in
accordance with values expected from theory (figure 2) for a
semi-infinite target. This behavior has influence on temperatures
measured with a spatial resolution of a few millimeters
and the calculated heat flux.
Lock-In thermography
Technical University of Munich
Lehrstuhl für Messsystem- und Sensortechnik
Head: Prof. Dr.-Ing. Alexander W. Koch
The simplest thermographic method is to heat up with a short
pulse of energy and to observe the decay of the temperature.
Figure 1 shows a result of this method. A more sophisticated
approach is Lock-In thermography. Instead of a short energy
pulse the sample is heated continuously using a periodically
modulated energy source. This results in the generation of a
thermal wave in the sample. This thermal wave can be characterized
by its amplitude and phase. Both, amplitude and phase,
are affected by the whole domain in which the wave has formed.
temperature / C
160
140
120
100
80
60
40
20
pixel
140
120
100
80
60
40
20
0
The cooperation of IPP and Technical University
of Munich is concentrated on the development
of thermography measurement techniques
for surface characterisation. In general thermography
is a means for temperature measurement
of a surface by monitoring the emitted
infrared radiation. With defined temperature
stimulation it is used as a non-destructive and
contact-less testing method.
0 20 40 60 80 100 120 140
pixel
Figure 1: Spatial temperature distribution on a CFC sample heated with a
32 ms Gaussian laser pulse (1 pixel = 30 μm)
113
A characteristic value is the thermal
diffusion length μ, which is
defined with f the frequency of
the modulation and α the thermal
diffusivity of the material as:
For good heat conductors μ is high, i.e. about 6 mm for copper
at a modulation frequency of 1 Hz, and low for bad heat
conductors like steel with about 1 mm.
(1)
(2)
Figure 2: Temperature devolution for one hot spot (1) and the homogeneous
area (2) in the center of the laser pulse
For the calculation of amplitude and phase four data points
are required, which are acquired at time differences of T/4
of the modulation period. With these four points the amplitude
A for the whole monitored surface can be calculated
according to
and the phase ϕ according to
⎛ I
ϕ
= arctan
⎜
⎝ I
1
2
−
−
(3)
Although both, amplitude and phase, are calculated from the
same four data points the phase data has two advantages:
• Amplitude data is sensitive down to a depth of about μ,
phase data up to 2μ.
I
I
3
4
⎞
⎟
⎟.
⎠

• Phase data is insensitive for inhomogeneous heating, variations
of the emission coefficient and similar negative
effects influencing the original temperature data.
The fact that the frequency dependent μ is a limit for the
sensitivity range can be used for depth probing by varying
the frequency systematically for both, amplitude and phase.
Setup
The surface temperature is measured using an infrared camera.
The camera is provided with a microscope objective for
a spatial resolution of about 30 μm. Frame rates above 1 kHz
are possible while observing an area of about 4×4 mm². For
the heating of the samples a fiber-coupled diode laser with
an output power of 80 W is used. The wavelength of the
laser radiation is in the near infrared at 980 nm. Because the
cameras are sensitive between 3 μm and 5 μm, reflected
heating power will not influence the measured signal. The
current through the laser diode and with it the output power
is controlled by an analog input voltage supplied by a frequency
generator for the modulation part and an additional
voltage source for the constant dc offset. Since the spot of
the focused laser beam has a diameter of about 2.8 mm an
average power density of above 10 MW/m² can be achieved.
Amplitude / K
60
40
20
pixel
250
200
150
100
50
0
Figure 3: Calculated amplitude for CFC sample
100 150 200 250 300
pixel
Applying Lock-In thermography to a CFC sample shows at
first the same inhomogeneous temperature distribution as for
pulsed heating. Taking a look at the time devolution shows
that for periodic heating both, the hot spots and the rest of the
sample, follow the modulation signal with a higher amplitude
for the hot spots. Calculating the amplitude and the phase
shows hot spots also in the amplitude image (figure 3) as expected,
but not in the phase image (figure 4), which is uniform.
Technical University of Munich
114
phase / rad
3
2
1
0
-1
-2
-3
pixel
250
200
150
100
50
Amplitude and phase calculations with (2) and (3) have two
drawbacks:
• Depending on the relation of the recording rate and the frequency
modulation it might not be possible to take data
points with an exact difference of T/4 of the modulation
period. This will result in an error which is not constant
over the whole area.
• Sometimes the recorded signal is not sinusoidal at all times
as assumed in the derivation of (2) and (3), e.g. if the camera
signal is saturated at temperatures. Even if half of the signal
would be still evaluable it is not possible to get reasonable
results with the given formulas.
To overcome these problems new algorithms for phase and
amplitude calculation have to been found which do not
require a fixed value of T/4.
Other activity
Another field of activity is the support for high heat flux
tests at the Materials Research division at the IPP. For the
new stellerator Wendelstein 7-X divertor target elements
will be tested in GLADIS, a testing facility with a high energy
hydrogen ion beam used to apply numerous heat load pulses
on each target element, to find defective ones before using them
in real fusion experiments. Because there are many elements,
a manual inspection of the recorded infrared data is not reasonable.
With the adaption of ASDEX Upgrade software for
thermographic data visualization and analysis, it will be
possible to automate most of the data analysis.
Scientific Staff
M. Jakobi, P. de Marné.
0
Figure 4: Calculated phase for CFC sample
100 150 200
pixel
250 300

ECRH in over-dense plasmas
University of Stuttgart
Institut für Plasmaforschung (IPF)
Head: Prof. Dr. Ulrich Stroth
The plasma in the torsatron TJ-K
is generated by microwaves at
2.45 GHz with a maximum power
of 6 kW and at 8 GHz with a
maximum power of 1.2 kW. The
plasma density usually exceeds
the cutoff density. With electron
temperatures of T e ≤20 eV, absorption
at the fundamental resonance
is found to be inefficient
for the O-wave as well as for the X-wave. This is true for
both heating frequencies. Hollow T e profiles observed in the
2.45-GHz-heated plasmas indicate power deposition at the
plasma boundary, more precisely at the upper hybrid resonance
(UHR). At the higher heating frequency the T e profiles
become more flat indicating an increased power deposition
at the plasma centre. This could be due to heating via
electron Bernstein waves (EBW). The EBWs can be generated
by the O-X-B mode-conversion process.
Figure 1: Simulation of the O-X-B conversion performed with a FDTD fullwave
code. Plotted is the positive value of the wave electric field.
This conversion process was investigated in detail with the
full-wave code IPF-FD3D. A simulation result is shown in
figure 1. The O-mode is incident at an optimum angle with
respect to the magnetic field lines from the lower left corner,
indicated by the black arrow. The density gradient is parallel
to the y-axis, the magnetic field parallel to the x-axis. At a
region around the O-mode cutoff the O-X conversion
occurs. The direction of propagation of the X-mode is indicated
by the grey arrow. The X-B conversion happens at the
UHR where the X-mode is converted into a backwards
propagating EBW with the direction of propagation indicated
by the light grey arrow. Furthermore does the formation
of the EBW take some time: several hundred wave periods
are necessary before the EBW reaches the O-mode cutoff.
The joint program between IPF and IPP on
ECRH systems for ASDEX Upgrade, W7-X,
and ITER can be found on the respective pages
of this annual report. Here is summarized the
part of the program carried out at IPF, which is
the development of new mm-wave components,
investigations of plasma waves and turbulent
transport. Experiments are carried out on the
torsatron TJ-K, which is operated with a magnetically
confined low-temperature plasma.
115
Array antenna for Bernsteinwave
heating
Bernstein waves are electrostatic
waves, which are efficiently absorbed
at the electron-cyclotron
resonance. They can be used to
heat over-dense plasmas, where
they can be created in a so-called
O-X-B mode conversion process.
The conversion efficiency depends
on the angle between the
wave vector and the direction of the magnetic field at the O-cutoff.
To investigate the O-X-B conversion process it is desirable
to have an antenna with a steerable characteristic.
The array antenna build for TJ-K has this capacity. In the
frequency range from 7.9 to 8.4 GHz the emitted wave vector
can be swept from -45° to +45°. Calculations of the O-X
conversion have shown that the optimal angle of incidence
of the microwave with respect to the magnetic field is about
-45°. The measured characteristics fits rather well the theoretical
one. The full width at half maximum of the pattern is
at about 20°. The power levels of the next maxima are about
20 dB below the main maximum. The main antenna loop
can be steered to an angle of -42° which is close to the optimum
value. Electron density measurements have shown that it is
possible to produce over-dense plasma with the new antenna.
The profile of the electron temperature of such over-dense
plasma is flat over the entire minor plasma radius. This
could be a sign of plasma heating due to Bernstein waves.
Deposition measurements are in progress and first results
show heating at the cyclotron resonance.
Influence of the adiabaticity parameter on the spectral
power transfer of density fluctuations
The investigation of the dual turbulent cascade in drift-wave
turbulence has been continued. Although being a one field
model, the bispectral technique developed by Kim et al. was
applied to 2D density and potential-fluctuation measurements,
where one field (potential) was analysed for the energy
(inverse) cascade and the other (density) for the enstrophy
(direct) cascade. In 2007, the validity of this approach has
been tested on simulated data from a Hasegawa-Wakatani
code. The key parameter for this study is the coupling coefficient
C~1/ν, which inversely depends on the electron-ion
collisionality ν. Simulation results were compared for a high
value of C=2 with the value valid of the experiment of C=1
and the result from the experimental data. In case of adiabatic
electrons (C=2), density and potential fluctuations are
strongly coupled and the spectral power of the density fluctuations
follows that of the potential fluctuations, which is
transferred as an inverse cascade to larger scales.

Most of the power transfer takes place at larger scales. For
experimental conditions (C=1), the direction of power transfer
of the density fluctuations has changed to the opposite
direction and one can identify a local direct cascade at
smaller scales, which is also expected for the enstrophy
transfer. This cascade is also present in the potential fluctuations,
but due to the weighting of the vorticity with k 2 it is
much more pronounced in the enstrophy cascade. The simulation
at the realistic value of C=1 agrees with the experimental
result.
Investigations of microwave material properties in a
three-mirror resonator configuration
For the construction of future fusion experiments like ITER
and W7-X, where long-pulse, high-power ECR applications
are planned, the definition of realistic cooling requirements
of mm-wave components is crucial. To enlarge the data base
on ohmic losses of reflectors due to finite conductivity,
imperfections of the material, and especially surface modifications
by long-term plasma exposition, various mirror samples
have been investigated at 140 and 170 GHz using a
three-mirror resonator. The losses depend on the position on
the mirror, confirming strong influence of plasma on the invessel
components. The absorption coefficients for 170 GHz,
E-plane, 45° angle of incidence for a ASDEX Upgrade mirror
are 0.36-0.44 % and for a W7-AS mirror 0.39-0.43 %.
Additional measurements of the W7-AS mirror surface with
a roughness detection instrument and spectroscopic analysis
confirmed the strong influence of different surface deposits
on mirrors, depending on the placement inside the torus.
Measurements on non-exposed W7-X TZM mirrors yield
comparable absorption with previous results for copper and
aluminium surfaces, all significantly lower (0.21 %) than for
the exposed samples.
Optimization of smooth-wall HE 11 Horn antennas
The existing waveguide codes were extended by a scattering
matrix module, which allows the calculation of mode conversions
due to diameter changes in cylindrical waveguides.
In contrast to the faster coupled mode equation algorithm,
the scattering matrix method does not neglect reflected
waves and is not limited to slight diameter variations. Based
on this, a program was developed, which optimizes the
function r(z) (r: waveguide radius, z: axial coordinate) for
given input- and output radii. Since mode conversion is
highly dependent on the phase differences of coupled modes,
the total length can also be changed by the optimizer. This
code can be used to optimize any kind of mode converter
with varying diameter. For a horn antenna, the wanted aperture
field is expanded into a spectrum of complex mode
amplitudes, which are then used as the optimization goal.
University of Stuttgart
116
Figure 2 shows the measured far field of an optimized horn
at 140 GHz in co- and cross polarization. The side-lobe level
is very low the level of cross-polarization, however, is -17 dB,
which is too high for some applications. The improvement
of the codes for better results is an ongoing task.
Figure 2: Far field of the horn antenna in co-polarization (left) and crosspolarization
Materials with negative index of refraction
The propagation of electromagnetic waves in waveguide
structures with negative index of refraction has been investigated
with a commercial full-wave solver (CST-Microwave
Studio). Calculations and experiments on waveguides with
different filling like thin wire structures, which exhibit behaviour
similar to plasma (negative permittivity), and/or
resonant structures like split rings (negative permeability)
have been performed. Especially, experiments on TM 11 waveguides
with wire structures confirmed the backward wave
propagation at resonant frequency.
For high-power applications in experimental plasma physics,
feasibility studies on application of the principle of a negative
refractive index, e.g. for backward-forward scanning
leaky-wave antennas and other microwave components have
been started. A design based on coaxial balanced CL-LC
transmission lines is proposed. The optimization of the
structures that allow high current-density handling, and
numerical simulations using CST are underway. The excitation
of backward waves based on coupled cavity chains was
shown. The back-fire to end-fire scanning capability of this
new metamaterial-based leaky-wave antenna for high power
applications was numerically confirmed.
Scientific Staff
P. Brand, G. Birkenmeier, E. Holzhauer, H. Höhnle, A. Jooß,
W. Kasparek, A. Köhn, H. Kumric, C. Lechte, N. Mahdizadeh,
P. Manz, B. Nold, B. Plaum, K. Rahbarnia, M. Ramisch,
L. Stollenwerk, U. Stroth.

Publications

Articles, Books and Inbooks
Adelhelm, C., M. Balden and M. Sikora: EXAFS investigations
of the thermally induced structuring of titanium doped amorphous
carbon films. Materials Science and Engineering C 27,
1423-1427 (2007).
Albajar, F., N. Bertelli, M. Bornatici and F. Engelmann: Electron-cyclotron
absorption in high-temperature plasmas: quasiexact
analytical evaluation and comparative numerical analysis.
Plasma Physics and Controlled Fusion 49, 15-29 (2007).
Albajar, F., M. Bornatici and F. Engelmann: Electron cyclotron
wave power loss in fusion plasmas: a model comparison.
Nuclear Fusion 47, 1101-1105 (2007).
Alimov, V. K. and J. Roth: Hydrogen isotope retention in
plasma-facing materials: Review of recent experimental
results. Physica Scripta T128, 6-13 (2007).
Allen, F. I., C. Biedermann, R. Radtke and G. Fußmann: Charge
exchange of highly charged argon ions as a function of projectile
energy. Journal of Physics. Conference Series 58,
188-191 (2007).
Angioni, C., L. Carraro, T. Dannert, N. Dubuit, R. Dux, C. Fuchs,
X. Garbet, L. Garzotti, C. Giroud, R. Guirlet, F. Jenko, O. Kardaun,
L. Lauro-Taroni, P. Mantica, M. Maslov, V. Naulin, R. Neu,
A. G. Peeters, G. Pereverzev, M. E. Puiatti, T. Pütterich, J. Stober,
M. Valovic, M. Valisa, H. Weisen, A. Zabolotsky, ASDEX Upgrade
Team and JET EFDA Contributors: Particle and Impurity
Transport in Axial Symmetric Divertor Experiment Upgrade and
the Joint European Torus, Experimental Observations and Theoretical
Understanding. Physics of Plasmas 14, 055905 (2007).
Angioni, C., R. Dux, E. Fable, A. G. Peeters and ASDEX
Upgrade Team: Non-adiabatic passing electron response
and outward impurity convection in gyrokinetic calculations
of impurity transport in ASDEX Upgrade plasmas. Plasma
Physics and Controlled Fusion 49, 2027-2043 (2007).
Angioni, C., H. Weisen, O. J. W. F. Kardaun, M. Maslov,
A. Zabolotsky, C. Fuchs, L. Garzotti, C. Giroud, B. Kurzan,
P. Mantica, A. G. Peeters, J. Stober, ASDEX Upgrade Team
and EFDA-JET Workprogramme: Scaling of density peaking
in H-mode plasmas based on a combined database of AUG
and JET observations. Nuclear Fusion 47, 1326-1335 (2007).
Balden, M. and C. Adelhelm: Characterization and erosion of metalcontaining
carbon films. Physica Scripta T128, 121-126 (2007).
Balden, M., C. Adelhelm, E. De Juan Pardo and J. Roth:
Chemical erosion by deuterium impact of carbon films
Publications
119
doped with nanometer-sized carbide crystallites. Journal of
Nuclear Materials 363-365, 1173-1178 (2007).
Balden, M., C. Adelhelm, T. Köck, A. Herrmann and J. Jaimerena-
Muga: Thermal nanostructuring of metal-containing carbon
films and their nanoindentation testing. Invited Paper.
Reviews on Advanced Materials Science 15, 95-104 (2007).
Balden, M., C. Adelhelm and M. Sikora: Thermal stability
and nano-structure of metal-doped carbon layers. Journal of
Nuclear Materials 367-370, 1458-1462 (2007).
Baldwin, M. J., R. P. Doerner, D. Nishijima, D. Buchenauer,
W. M. Clift, R. A. Causey and K. Schmid: Be-W alloy formation
in static and divertor-plasma simulator experiments.
Journal of Nuclear Materials 363-365, 1179-1183 (2007).
Barradas, N. P., K. Arstila, G. Battistig, M. Bianconi,
N. Dytlewski, C. Jeynes, E. Kotai, G. Lulli, M. Mayer, E. Rauhala,
E. Szilagyi and M. Thompson: International Atomic Energy
Agency intercomparison of ion beam analysis software. Nuclear
Instruments and Methods in Physics Research B: Beam
Interactions with Materials and Atoms 262, 281-303 (2007).
Becker, G. and O. Kardaun: Anomalous Particle Pinch and
Scaling of ν in /D Based on Transport Analysis and Multiple
Regression. Nuclear Fusion 47, 33-43 (2007).
Behrisch, R. and W. Eckstein (Eds.): Sputtering by Particle
Bombardment: Experiments and Computer Calculations from
Threshold to MeV Energies. Topics in Applied Physics 110.
Springer Verlag, Berlin (2007) 508 p.
Behrisch, R. and W. Eckstein: Introduction and Overview.
Sputtering by Particle Bombardment: Experiments and
Computer Calculations from Threshold to MeV Energies.
(Eds.) R. Behrisch, W. Eckstein. Topics in Applied Physics 110.
Springer Verlag, Berlin, 1-20 (2007).
Benito, A., D. Goitia, E. Casado, M. Anderez, E. Vázquez,
M. Fajardo, C. Palacios, A. Cardella, D. Pilopp, L. Giordano
and G. Di Bartolo: Manufacturing of the coil support structure
for W7-X. Fusion Engineering and Design 82, 1579-1583
(2007).
Biedermann, C. and R. Radtke: Comment on “Direct observation
of the 2 D 3/2 – 2 D 5/2 ground-state splitting in Xe 9+ ”.
Physical Review A 75, 066501 (2007).
Biedermann, C., R. Radtke, G. Fußmann and F. I. Allen:
Extreme ultraviolet spectroscopy of highly charged argon
ions at the Berlin EBIT. Journal of Physics. Conference
Series 72, 012004 (2007).

Bierwage, A. and Q. Yu: Comparison between resistive and
collisionless double tearing modes for nearby resonant surfaces.
Plasma Physics and Controlled Fusion 49, 675-688
(2007).
Bierwage, A., Q. Yu and S. Günter: Large-Mode-Number
Magnetohydrodynamic Instability Driven by Sheared Flows
in a Tokamak Plasma with Reversed Central Shear. Physics
of Plasmas 14, 010704 (2007).
Bin, W., A. Bruschi, S. Cirant, V. Erckmann, F. Gandini,
G. Granucci, F. Hollmann, H. P. Laqua, V. Mellera, V. Muzzini,
A. Nardone, F. Noke, B. Piosczyk, F. Purps, T. Rzesnicki,
M. Schmid, C. Sozzi, W. Spies, N. Spinicchia and M. Stoner:
Advances in high power calorimetric matched loads for short
pulses and CW gyrotrons. Fusion Engineering and Design 82,
775-784 (2007).
Birus, D., T. Rummel, M. Fricke, K. Petry and H. Demattio:
Development of Quench Detection System for W7-X.
Fusion Engineering and Design 82, 1400-1405 (2007).
Bizyukov, I. and K. Krieger: Transition from tungsten erosion
to carbon layer deposition with simultaneous bombardment
of tungsten by helium and carbon. Journal of Applied
Physics 101, 104906 (2007).
Bizyukov, I. and K. Krieger: Principal processes occuring at
simultaneous bombardment of tungsten by carbon and deuterium
ions. Journal of Applied Physics 102, 074923 (2007).
Bizyukov, I., K. Krieger, A. Azarenkov, S. Levchuk and
C. Linsmeier: Tungsten sputtering and accumulation of implanted
carbon and deuterium by simultaneous bombardment
with D and C ions. Journal of Nuclear Materials 363-365,
1184-1889 (2007).
Bobkov, V. V., F. Braun, R. Dux, A. Herrmann, A. Kallenbach,
R. Neu, J.-M. Noterdaeme, T. Pütterich and ASDEX Upgrade
Team: Compatibility of ICRF antennas with W-coated limiters
for different plasma geometries in ASDEX Upgrade.
Journal of Nuclear Materials 363-365, 122-126 (2007).
Bohmeyer, W., A. Markin, D. Naujoks, B. Koch, G. Krenz,
M. Baudach and G. Fußmann: Decomposition and sticking
of hydrocarbons in the plasma generator PSI-II. Journal of
Nuclear Materials 363-365, 127-130 (2007).
Boscary, J., B. Böswirth, H. Greuner, P. Grigull, M. Missirlian,
A. Plankensteiner, B. Schedler, T. Friedrich, J. Schlosser,
B. Streibl and H. Traxler: Fabrication and testing of W7-X
pre-series target elements. Physica Scripta T128, 195-199
(2007).
Publications
120
Boscary, J., B. Böswirth, H. Greuner, M. Missirlian,
B. Schedler, K. Scheiber, J. Schlosser and B. Streibl: Results
of the examinations of the W7-X pre-series target elements.
Fusion Engineering and Design 82, 1634-1638 (2007).
Bottino, A., A. G. Peeters, R. Hatzky, S. Jolliet, B. F. McMillan,
T. M. Tran and L. Villard: Nonlinear Low Noise Particle-incell
Simulations of Electron Temperature Gradient Driven
Turbulence. Physics of Plasmas 14, 010701 (2007).
Brambilla, M.: Quasilinear Description of Radiofrequencyinduced
Radial Diffusion. Nuclear Fusion 47, 175-180 (2007).
Braune, H., P. Brand, V. Erckmann, L. Jonitz, W. Leonhardt,
D. Mellein, G. Michel, G. Müller, F. Purps, K.-H. Schlüter,
M. Winkler, W7-X ECRH Team at IPP, W7-X ECRH Team at
IPF and W7-X ECRH Team at FZK: Architecture of central
control system for the 10 MW ECRH-plant at W7-X. Fusion
Engineering and Design 82, 677-685 (2007).
Brendel, A., C. Popescu, T. Köck and H. Bolt: Promising composite
heat sink material for the divertor of future fusion reactors.
Journal of Nuclear Materials 367-370, 1476-1480 (2007).
Brezinsek, S., A. Pospieszczyk, D. Borodin, M. F. Stamp,
R. Pugno, A. G. McLean, U. Fantz, A. Manhard, A. Kallenbach,
N. H. Brooks, M. Groth, P. Mertens, V. Philipps, U. Samm,
TEXTOR Group, ASDEX Upgrade Group, DIII-D Teams
and JET-EFDA Contributors: Hydrocarbon injection for
quantification of chemical erosion yields in tokamaks.
Journal of Nuclear Materials 363-365, 1119-1128 (2007).
Brezinsek, S., R. Pugno, U. Fantz, A. Manhard, H. W. Müller,
A. Kallenbach, P. Mertens and ASDEX Upgrade Team:
Determination of photon efficiencies and hydrocarbon
influxes in the detached outer divertor plasma of ASDEX
Upgrade. Physica Scripta T128, 40-44 (2007).
Bronold, F. X., K. Matyash, D. Tskhakaya, R. Schneider and
H. Fehske: Radio-frequency discharges in oxygen: I. Particlebased
modelling. Journal of Physics D 40, 6583-6592 (2007).
Budke, M., V. Renken, H. Liebl, G. Rangelov and M. Donath:
Inverse photoemission with energy resolution better than
200 meV. Review of Scientific Instruments 78, 083903 (2007).
Busse, A., W.-C. Müller, H. Homann and R. Grauer: Statistics
of passive tracers in three-dimensional magnetohydrodynamic
turbulence. Physics of Plasmas 14, 122303 (2007).
Bykov, V., F. Schauer, K. Egorov, P. van Eeten, C. Damiani,
A. Dübner, M. Sochor, L. Sonnerup, A. Capriccioli, A. Tereshchenko,
N. Jaksic, W. Dänner, M. Rumyancev and D. Zacharias:

Structural analysis of W7-X: Main results and critical issues.
Fusion Engineering and Design 82, 1538-1548 (2007).
Camenen, Y., A. Pochelon, R. Behn, A. Bottino, A. Bortolon, S. Coda,
A. Karpushov, O. Sauter, G. Zhuang and TCV Team: Impact of
Plasma Trangularity and Collisionality on Electron Heat Transport
in TCV L-mode Plasmas. Nuclear Fusion 47, 510-517 (2007).
Cardella, A., B. Hein, D. Hermann, T. Koppe, B. Missal,
D. Pilopp, J. Reich, M. Wanner, H. Jenzsch, R. Krause,
B. Plöckl, G. Di Bartolo, F. Leher, A. Binni, J. Segl, A. Benito,
L. Giordano and S. Langone: Construction of the vacuum vessels
and the magnet supporting structures of Wendelstein 7-X.
Fusion Engineering and Design 82, 1911-1916 (2007).
Casati, A., P. Mantica, D. Van Eester, N. Hawkes, F. Imbeaux,
E. Joffrin, A. Marinoni, F. Ryter, A. Salmi, T. Tala, P. De Vries
and JET-EFDA Contributors: Critical temperature gradient
length signatures in heat wave propagation across internal
transport barriers in the Joint European Torus. Physics of
Plasmas 14, 092303 (2007).
Chankin, A. V., D. P. Coster, N. Asakura, X. Bonnin, G. D. Conway,
G. Corrigan, S. K. Erents, W. Fundamenski, J. Horacek,
A. Kallenbach, M. Kaufmann, C. Konz, K. Lackner, H. W. Müller,
J. Neuhauser, R. A. Pitts and M. Wischmeier: Discrepancy
between modelled and measured radial electric fields in the
scrape-off layer of divertor tokamaks: a challenge for 2D
fluid codes? Nuclear Fusion 47, 479-489 (2007).
Chankin, A. V., D. P. Coster, R. Dux, C. Fuchs, G. Haas,
A. Herrmann, L. D. Horton, A. Kallenbach, M. Kaufmann,
A. S. Kukushkin, K. Lackner, H. W. Müller, J. Neuhauser,
R. Pugno, M. Tsalas and ASDEX Upgrade Team: Comparison
between measured divertor parameters in ASDEX
Upgrade and SOLPS code simulations. Journal of Nuclear
Materials 363-365, 335-340 (2007).
Chankin, A. V., D. P. Coster, N. Asakura, G. Corrigan, S. K. Erents,
W. Fundamenski, H. W. Müller, R. A. Pitts, P. C. Stangeby
and M. Wischmeier: A possible role of radial electric field in
driving parallel ion flow in scrape-off layer of divertor
tokamaks. Nuclear Fusion 47, 762-772 (2007).
Chen, Y. P., G. S. Xu, J. S. Hu and D. P. Coster: Edge plasma
modelling for HT-7 superconducting tokamak experiments.
Journal of Nuclear Materials 363-365, 544-549 (2007).
Coad, J. P., P. Andrew, S. K. Erents, D. E. Hole, J. Likonen,
M. Mayer, R. Pitts, M. Rubel, J. D. Strachan, E. Vainonen-
Ahlgren, A. Widdowson and JET-EFDA Contributros: Erosion
and deposition in the JET MkII-SRP divertor. Journal of
Nuclear Materials 363-365, 287-293 (2007).
Publications
121
Colas, L., A. Ekedahl, M. Goniche, J. P. Gunn, B. Nold, Y. Corre,
V. Bobkov, R. Dux, F. Braun, J.-M. Noterdaeme, M.-L. Mayoral,
K. Kirov, J. Mailloux, S. Heuraux, E. Faudot, J. Ongena,
ASDEX Upgrade Team and JET-EFDA Contributors: Understanding
the spatial structure of RF-induced SOL modifications.
Invited Paper. Plasma Physics and Controlled Fusion 49,
B35-B45 (2007).
Connor, J. W., C. Angioni, P. H. Diamond, G. W. Hammett,
C. Hidalgo, A. Loarte and P. Mantica: 11 th EU-US Transport
Task Force workshop on transport in fusion plasmas. Nuclear
Fusion 47, 361-369 (2007).
Conway, G. D.: Report on the Eight International Reflectometry
Workshop (IRW8) (St Petersburg, Russia, 2-4 May 2007).
Nuclear Fusion 47, 1710-1714 (2007).
Coster, D. P., X. Bonnin, A. Mutzke, R. Schneider and M. Warrier:
Integrated modelling of the edge plasma and plasma facing
components. Journal of Nuclear Materials 363-365, 136-139
(2007).
Crowley, B., D. Homfray, U. Fantz, D. Boilson and R. S. Hemsworth:
Electron energy distribution function measurements by Langmuir
probe in ITER like negative ion sources. Production and
Neutralization of Negative Ions and Beams. (Ed.) M. P. Stockli.
AIP Conference Proceedings 925. American Institute of Physics,
Melville, NY, 193-207 (2007).
Czymek, G., B. Giesen, F. Harberts, A. Panin, M. Lennartz,
U. Reisgen, W. Schuster, J. Wolters, K. Rummel, M. Czerwinski,
H. Lentz and M. Ebner: Design aspects of the joints for the
bus bar system of the Wendelstein 7-X stellarator. Fusion
Engineering and Design 82, 1467-1472 (2007).
Da Graça, S., G. D. Conway, P. Lauber, M. Maraschek,
D. Borba, S. Günter, L. Cupido, K. Sassenberg, F. Serra,
M. E. Manso, CFN Reflectometry Group and ASDEX Upgrade
Team: Localization of MHD and fast particle modes using
reflectometry in ASDEX Upgrade. Plasma Physics and Controlled
Fusion 49, 1849-1872 (2007).
De Termmerman, G., M. J. Baldwin, R. P. Doerner, D. Nishijima,
R. Seraydarian, K. Schmid, F. Kost, C. Linsmeier and L. Marot:
Beryllium deposition on International Thermonuclear
Experimental Reactor first mirrows: Layer morphology and
influence on mirror reflectivity. Journal of Applied Physics 102,
083302 (2007).
Dewar, R. L., B. G. Kenny, C. Nührenberg, T. Tatsuno and
B. F. McMillan: Quantum Chaos? Genericity and Nongenericity
in the MHD Spectrum of Nonaxisymmetric Toroidal Plasmas.
Journal of the Korean Physical Society 50, 112-117 (2007).

Dimits, A. M., W. M. Nevins, D. E. Shumaker, G. W. Hammett,
T. Dannert, F. Jenko, M. J. Pueschel, W. Dorland, S. C. Cowley,
J. N. Lebouef, T. L. Rhodes, J. Candy and C. Estrada-Mila:
Gyrokinetic simulations of ETG and ITG turbulence.
Nuclear Fusion 47, 817-824 (2007).
Dinklage, A., E. Ascasibar, C. D. Beidler, J. Geiger, J. H. Harris,
A. Kus, S. Murakami, S. Okamura, R. Preuss, F. Sano, U. Stroth,
Y. Suzuki, J. Talmadge, V. Tribaldos, K. Y. Watanabe, H. Yamada
and M. Yokoyama: Assessment of Global Stellarator Confinement:
Status of the International Stellarator Confinement
Scaling Data Base. Fusion Science and Technology 51, 1-7 (2007).
Dinklage, A., H. Maaßberg, R. Preuss, Y. Turkin, H. Yamada,
E. Ascasibar, C.D. Beidler, H. Funaba, J. H. Harris, A. Kus,
S. Murakami, S. Okamura, F. Sano, U. Stroth, Y. Suzuki,
J. Talmadge, V. Tribaldos, K. Y. Watanabe, A. Werner, A. Weller
and M. Yokoyama: Physical model assessment of the energy
confinement time scaling in stellarators. Nuclear Fusion 47,
1265-1273 (2007).
Dobosz, R., A. Cardella, M. Wanner, G. Dell’Orco and A. Opitz:
The draining and drying experiments for the plasma vessel
cooling pipes of the Wendelstein 7-X stellarator. Fusion
Engineering and Design 82, 2067-2072 (2007).
Doerner, R. P., M. Baldwin, J. Hanna, C. Linsmeier, D. Nishijima,
R. Pugno, J. Roth, K. Schmid and A. Wiltner: Interaction of
beryllium containing plasma with ITER materials. Physica
Scripta T128, 115-120 (2007).
Donne, A. J. H., A. E. Costley, R. Barnsley, H. Bindslev,
R. Boivin, G. Conway, R. Fisher, R. Gianella, H. Hartfuß,
M. G. von Hellermann, E. Hodgson, L. C. Ingesson, K. Itami,
D. Johnson, Y. Kawano, T. Kondoh, A. Krasilnikov, Y. Kusama,
A. Litnovsky, P. Lotte, P. Nielsen, T. Nishitani, F. Orsitto,
B. J. Peterson, G. Razdobarin, J. Sanchez, M. Sasao, T. Sugie,
G. Vayakis, V. Voitsenya, K. Vukolov, C. Walker, K. Young and
ITPA Topical Group on Diagnostics: Chapter 7: Diagnostics.
Nuclear Fusion 47, S337-S384 (2007).
Dose, V.: Bayesian estimate of the Newtonian constant of gravitation.
Measurement Science and Technology 18, 176-182 (2007).
Dose, V.: Reply to the comment on “Bayesian estimate of
the Newtonian constant of gravitation”. Measurement Science
and Technology 18, 2281-2282 (2007).
Doyle, E. J., W. A. Houlberg, Y. Kamada, V. Mukhovatov,
T. H. Osborne, A. Polevoi, G. Bateman, J. W. Connor,
J. G. Cordey, T. Fujita, X. Garbet, T. S. Hahm, L. D. Horton,
A. E. Hubbard, F. Imbeaux, F. Jenko, J. E. Kinsey, Y. Kishimoto,
J. Li, T. C. Luce, Y. Martin, M. Ossipenko, V. Parail, A. Peeters,
Publications
122
T. L. Rhodes, J. E. Rice, C. M. Roach, V. Rozhansky, F. Ryter,
G. Saibene, R. Sartori, A. C. C. Sips, J. A. Snipes, M. Sugihara,
E. J. Synakowski, H. Takenaga, T. Takizuka, K. Thomsen,
M. R. Wade, H. R. Wilson, ITPA Confinement Database and
Modelling Topical Group and ITPA Pedestal and Edge Topical
Group: Chapter 2: Plasma confinement and transport. Nuclear
Fusion 47, S18-S127 (2007).
Dudek, A., A. Benndorf, V. Bykov, A. Cardella, C. Damiani,
A. Dübner, W. Dänner, M. Gasparotto, T. Höschen, G. Matern,
D. Pilopp, F. Schauer, L. Sonnerup, J. Wendorf and C. Zauner:
Tests of the critical bolted connection of the Wendelstein 7-X
coils. Fusion Engineering and Design 82, 1500-1507 (2007).
Durocher, A., F. Escourbiac, A. Grosman, J. Boscary, M. Merola,
F. Cismondi, X. Courtois, J. L. Farjon, M. Missirlian, J. Schlosser
and R. Tivey: Advanced qualification methodology for actively
cooled plasma facing components. Nuclear Fusion 47,
1682-1689 (2007).
Durocher, A., J. Moysan, F. Escourbiac, M. Missirlian,
N. Vignal and J. Boscary: Infrared images data merging for
plasma-facing component inspection. Fusion Engineering
and Design 82, 1694-1699 (2007).
Dux, R., V. Bobkov, N. Fedorczak, K. Iraschko, A. Kallenbach,
R. Neu, T. Pütterich, V. Rohde and ASDEX Upgrade: Tungsten
erosion at the ICRH limiters in ASDEX Upgrade. Journal of
Nuclear Materials 363-365, 112-116 (2007).
Eckstein, W.: Sputtering Yields. Sputtering by Particle Bombardment:
Experiments and Computer Calculations from Threshold
to MeV Energies. (Eds.) R. Behrisch, W. Eckstein. Topics in
Applied Physics 110. Springer Verlag, Berlin 33-187 (2007).
Eckstein, W. and H. M. Urbassek: Computer Simulation of
the Sputtering Process. Sputtering by Particle Bombardment:
Experiments and Computer Calculations from Threshold to
MeV Energies. (Eds.) R. Behrisch, W. Eckstein. Topics in
Applied Physics 110. Springer Verlag, Berlin 21-31 (2007).
Ehmler, H., J. Baldzuhn, L. Genini, K. Heyn, C. Sborchia,
T. Schild and W7-X Team: Review of the acceptance tests of
the W7-X superconducting magnets. Fusion Engineering
and Design 82, 1406-1412 (2007).
Ehmler, H. and M. Koeppen: AC modeling and impedance
spectrum tests of the superconducting magnetic field coils
for the Wendelstein 7-X fusion experiment. Review of
Scientific Instruments 78, 104705 (2007).
Eich, T., P. Andrew, A. Herrmann, W. Fundamenski, A. Loarte,
R. A. Pitts and JET-EFDA Contributors: ELM resolved

energy distribution studies in the JET MKII Gas-Box divertor
using infra-red thermography. Plasma Physics and Controlled
Fusion 49, 573-604 (2007).
Eich, T., A. Kallenbach, R. A. Pitts, S. Jachmich, J. C. Fuchs,
A. Herrmann, J. Neuhauser, ASDEX Upgrade Team and JET-
EFDA Contributors: Divertor power deposition and target current
asymmetries during type-I ELMS in ASDEX Upgrade and
JET. Journal of Nuclear Materials 363-365, 989-993 (2007).
Erckmann, V., P. Brand, H. Braune, G. Dammertz, G. Gantenbein,
W. Kasparek, H. P. Laqua, H. Maaßberg, N. B. Marushchenko,
G. Michel, M. Thumm, Y. Turkin, M. Weißgerber, A. Weller,
W7-X ECRH Team and IPF Stuttgart: Electron Cyclotron
Heating for W7-X: Physics and Technology. Fusion Science
and Technology 52, 291-312 (2007).
Eule, S., R. Friedrich and F. Jenko: Anomalous Diffusion of
Particles with Inertia in External Potentials. Journal of
Physical Chemistry B 111, 13041-13046 (2007).
Eule, S., R. Friedrich, F. Jenko and D. Kleinhans: Langevin
Approach to Fractional Diffusion Equations Including
Inertial Effects. Journal of Physical Chemistry B 111,
11474-11477 (2007).
Fantz, U., P. Franzen, W. Kraus, M. Berger, S. Christ-Koch,
M. Fröschle, R. Gutser, B. Heinemann, C. Martens, P. McNeely,
R. Riedl, E. Speth and D. Wünderlich: Negative ion RF
sources for ITER NBI: status of the deveopment and recent
achievements. Invited Paper. Plasma Physics and Controlled
Fusion 49, B563-B580 (2007).
Fasoli, A., C. Gormenzano, H. L. Berk, B. Breizman, S. Briguglio,
D. S. Darrow, N. Gorelenkov, W. W. Heidbrink, A. Jaun,
S. V. Konovalov, R. Nazikian, J.-M. Noterdaeme, S. Sharapov,
K. Shinohara, D. Testa, K. Tobita, Y. Todo, G. Vlad and F. Zonca:
Chapter 5: Physics of energetic ions. Nuclear Fusion 47,
S264-S284 (2007).
Federici, G., O. Zolotukhin, M. Kobayashi, A. Loarte,
G. Strohmayer, A. Tanga, A. Portone, L. Horton, Y. Feng,
F. Sardei, Y. Gribov, M. Shimada, A. Polevoi, R. Mitteau and
C. Lowry: Simulations of ITER start-up and assessment of
limiter power loads. Journal of Nuclear Materials 363-365,
346-352 (2007).
Feifel, R., T. Tanaka, M. Kitajima, H. Tanaka, A. De Fanis,
R. Sankari, L. Karlsson, S. Sorensen, M.-N. Piancastelli,
G. Prümper, U. Hergenhahn and K. Ueda: Probing the
valence character of O 1s → Rydberg excited O 2 by participator
Auger decay and mass-selected X-ray absorption spectroscopy.
Journal of Chemical Physics 126, 174304 (2007).
Publications
123
Feist, J.-H., H.-J. Bramow, R. Brockmann, G. Gliege, D. Grünberg,
T. Kluck, D. Pohle, M. Schroeder, R. Schult and R. Vilbrandt:
Quality management for Wendelstein 7-X – Lessons learned.
Fusion Engineering and Design 82, 2838-2843 (2007).
Feng, Y., F. Sardei, P. Grigull, K. McCormick, J. Kißlinger,
D. Reiter and D. Harting: Numerical Study on CX-Neutral
Transport and Wall-Sputtering in W7-AS Diverted Plasmas.
Journal of Nuclear Materials 363-365, 353-358 (2007).
Fischer, R. and A. Dinklage: The concept of Integrated Data
Analysis of complementary experiments. Bayesian Inference
and Maximum Entropy Methods in Science and Engineering:
27 th International Workshop on Bayesian Inference and Maximum
Entropy Methods in Science and Engineering. (Eds.)
K. H. Knuth, A. Caticha, J. L. Center, A. Giffin, C. C. Rodriguez.
AIP Conference Proceedings 954. American Institute of
Physics, Melville, NY, 195-202 (2007).
Franzen, P., H. D. Falter, U. Fantz, W. Kraus, M. Berger,
S. Christ, M. Fröschle, R. Gutser, B. Heinemann, S. Hilbert,
S. Leyer, A. Lümkemann, C. Martens, P. McNeely, R. Riedl,
E. Speth and D. Wünderlich: Progress of the Development
of the IPP RF Negative Ion Source for the ITER Neutral
Beam System. Nuclear Fusion 47, 264-270 (2007).
Franzen, P., H. D. Falter, B. Heinemann, Ch. Martens, U. Fantz,
M. Berger, S. Christ-Koch, M. Fröschle, D. Holtum, W. Kraus,
P. McNeely, R. Riedl, R. Süss, S. Obermayer, E. Speth and
D. Wünderlich: RADI – a RF source size-scaling experiment
towards the ITER neutral beam negative ion source.
Fusion Engineering and Design 82, 407-423 (2007).
Fröschle, M., S. Leyer, P. Franzen, C. Martens, E. Speth,
B. Heinemann, H. D. Falter, U. Fantz, W. Kraus and R. Riedl:
Technical overview and first results of the half-size ITER
NNBI source. Fusion Engineering and Design 82, 887-896
(2007).
Füllenbach, F., T. Rummel, S. Pingel, H. Laqua, I. Müller
and E. Jauregi: Final test of the W7-X control coils power
supply and its integration into the overall control environment.
Fusion Engineering and Design 82, 1391-1395 (2007).
Fujisawa, A., T. Ido, A. Shimizu, S. Okamura, K. Matsuoka,
H. Iguchi, Y. Hamada, H. Nakano, S. Ohshima, K. Itoh, K. Hoshino,
K. Shinohara, Y. Miura, Y. Nagashima, S.-I. Itoh, M. Shats,
H. Xia, J. Q. Dong, L. W. Yan, K. J. Zhao, G. D. Conway, U. Stroth,
A. V. Melnikov, L. G. Elisseev, S. E. Lysenko, S. V. Perfilov,
C. Hidalgo, G. R. Tynan, C. Holland, P. H. Diamond, G. R. McKee,
R. J. Fonck, D. K. Gupta and P. M. Schoch: Experimental
progress on zonal flow physics in toroidal plasmas. Nuclear
Fusion 47, S718-S726 (2007).

Fundamenski, W., J. Mlynar and M. Wischmeier: Focus On:
Plasma Edge. JET, Culham (2007).
http://www.jet.efda.org/pages/focus/plasma-edge/index.html
Gaio, E., W. Kraus, C. Martens, R. Piovan, E. Speth and V. Toigo:
Studies on the radio frequency power supply system for the
ITER NB injector ion source. Fusion Engineering and
Design 82, 912-919 (2007).
Garcia-Munoz, M., P. Martin, H.-U. Fahrbach, M. Gobbin,
S. Günter, M. Maraschek, L. Marrelli, H. Zohm and ASDEX
Upgrade Team: NTM induced fast ion losses in ASDEX
Upgrade. Nuclear Fusion 47, L10-L15 (2007).
Giesen, B., A. Panin, T. Boguzewski, S. Brons, A. Charl, G. Czymek,
A. John, O. Neubauer, M. Sauer, R. Schick, J. Szlagowska
and J. Wolters: Structural evaluation of the busbar system of
Wendelstein 7-X stellarator. Fusion Engineering and Design 82,
1591-1598 (2007).
Goetz, M., R. Meyer-Spasche and H. Weitzner: A study of
simple gyrotron. Journal of Physics A: Mathematical and
Theoretical 40, 2203-2218 (2007).
Golubeva, A., M. Mayer, J. Roth, V. Kurnaev and O. Ogorodnikova:
Deuterium retention in rhenium-doped tungsten. Journal of
Nuclear Materials 363-365, 893-897 (2007).
Gormezano, C., A. C. C. Sips, T. C. Luce, S. Ide, A. Becoulet,
X. Litaudon, A. Isayama, J. Hobirk, M. R. Wade, T. Oikawa,
R. Prater, A. Zvonkov, B. Lloyd, T. Suzuki, E. Barbato, P. Bonoli,
C. K. Phillips, V. Vdovin, E. Joffrin, T. Casper, J. Ferron,
D. Mazon, D. Moreau, R. Bundy, C. Kessel, A. Fukuyama,
N. Hayashi, F. Imbeaux, M. Murakami, A. R. Polevoi and
H. E. St John: Chapter 6: Steady state operation. Nuclear
Fusion 47, S285-S336 (2007).
Grandgiard, V., Y. Sarazin, P. Angelino, A. Bottino, N. Crouseilles,
G. Darmet, G. Dif-Pradalier, X. Garbet, P. Ghendrih, S. Jolliet,
G. Latu, E. Sonnendrücker and L. Villard: Global full-f
gyrokinetic simulations of plasma turbulence. Invited Paper.
Plasma Physics and Controlled Fusion 49, B173-B182 (2007).
Greuner, H., B. Boeswirth, J. Boscary, A. Leuprecht and
A. Plankensteiner: Power load limits of the Wendelstein 7-X
target elements – comparison of experimental results and
design values for power loads up to the critical heat flux.
Physica Scripta T128, 218-221 (2007).
Greuner, H., B. Boeswirth, J. Boscary and P. McNeely: High
Heat Flux Facility GLADIS – Operational Characteristics
and Results of W7-X Pre-Series Target Tests. Journal of
Nuclear Materials 367-370, 1444-1448 (2007).
Publications
124
Greuner, H., B. Boeswirth, J. Boscary, A. Plankensteiner
and B. Schedler: High heat flux tests of the Wendelstein 7-X
pre-series target elements – Experimental evaluation of the
thermo-mechanical behaviour. Fusion Engineering and
Design 82, 1713-1719 (2007).
Gribov, Y., D. Humphreys, K. Kajiwara, E. A. Lazarus, J. B. Lister,
T. Ozeki, A. Portone, M. Shimada, A. C. C. Sips and J. C. Wesley:
Chapter 8: Plasma operation ans control. Nuclear Fusion 47,
S385-S403 (2007).
Grisolia, C., G. Counsell, G. Dinescu, A. Semerok, N. Bekris,
P. Coad, C. Hopf, J. Roth, M. Rubel, A. Widdowson, E. Tsitrone
and JET EFDA Contributors: Treatment of ITER plasma
facing components: Current status and remaining open
issues before ITER implementation. Fusion Engineering
and Design 82, 2390-2398 (2007).
Gruber, O. and ASDEX Upgrade Team: Overview of ASDEX
Upgrade Results. Nuclear Fusion 47, S622-S634 (2007).
Grulke, O., A. Stark, T. Windisch, J. Zalach and T. Klinger:
Plasma profiles in a cylindrical helicon discharge with converging
magnetic source field. Contributions to Plasma
Physics 47, 183-189 (2007).
Grulke, O., S. Ulrich, T. Windisch and T. Klinger: Laboratory
studies of drift waves: nonlinear mode interaction and
structure formation in turbulence. Invited Paper. Plasma
Physics and Controlled Fusion 49, B247-B257 (2007).
Günter, S., G. Conway, S. da Graca, H.-U. Fahrbach, C. Forest,
M. Garcia Munoz, T. Hauff, J. Hobirk, V. Igochine, F. Jenko,
K. Lackner, P. Lauber, P. McCarthy, M. Maraschek, P. Martin,
E. Poli, K. Sassenberg, E. Strumberger, G. Tardini, E. Wolfrum,
H. Zohm and ASDEX Upgrade Team: Interaction of energetic
particles with large and small scale instabilities. Nuclear
Fusion 47, 920-928 (2007).
Günter, S. and K. Lackner: Wie bändigt man heißes Plasma?
Plasmaeinschluss in Fusionsexperimenten. Physik in unserer
Zeit 38, 134-140 (2007).
Günter, S., K. Lackner and C. Tichmann: Finite element and
higher order difference formulations for modelling heat
transport in magnetised plasmas. Journal of Computational
Physics 226, 2306-2316 (2007).
Gulejova, B., R. A. Pitts, M. Wischmeier, R. Behn, D. Coster,
J. Horacek and J. Marki: SOLPS5 modelling of the type III
ELMing H-mode on TCV. Journal of Nuclear Materials
363-365, 1037-1053 (2007).

Hacquin, S., S. E. Sharapov, B. Alper, C. D. Challis, A. Fonseca,
E. Mazzucato, A. Meigs, L. Meneses, I. Nunes, S. D. Pinches
and JET EFDA Contributors: Localized X-mode reflectometry
measurements of Alfvén eigenmodes on the JET tokamak.
Plasma Physics and Controlled Fusion 49, 1371-1390 (2007).
Hallatschek, K.: Nonlinear three-dimensional flows in magnetized
plasmas. Invited Paper. Plasma Physics and Controlled
Fusion 49, B137-B148 (2007).
Hartmann, D. A., R. Krampitz, C. Damiani, U. Neuner and
F. Schauer: Wendelstein 7-X Torus Hall Layout and System
Integration. Fusion Engineering and Design 82, 583-589 (2007).
Hatzky, R., A. Könies and A. Mishchenko: Electromagnetic
gyrokinetic PIC simulation with an adjustable control variates
method. Journal of Computational Physics 225, 568-590 (2007).
Hauff, T. and F. Jenko: E×B advection of trace ions in tokamak
microturbulence. Physics of Plasmas 14, 092301 (2007).
Hauff, T., F. Jenko and S. Eule: Intermediate non-Gaussian
transport in plasma core turbulence. Physics of Plasmas 14,
102316 (2007).
Hayashi, T., K. Sugiyama, K. Krieger, M. Mayer, V. Alimov,
T. Tanabe, K. Masaki and N. Miya: Deuterium depth profiling
in JT-60U tiles using the D 3 (He,p) 4 He resonant nuclear
reaction. Journal of Nuclear Materials 363-365, 904-909
(2007).
Heidinger, R., I. Danilov, A. Meier, B. Piosczyk, B. Späh,
M. Thumm, W. Bongers, M. Graswinckel, M. Henderson,
F. Leuterer, A. G. A. Verhoeven and D. Wagner: Development
of high power window prototypes for ECH&CD launchers.
Fusion Engineering and Design 82, 693-699 (2007).
Helander, P.: On rapid rotation in stellarators. Physics of
Plasmas 14, 104501 (2007).
Hender, T. C., J. C. Wesley, J. Bialek, A. Bondeson, A. H. Boozer,
R. J. Buttery, A. Garofalo, T. P. Goodman, R. S. Granetz, Y. Gribov,
O. Gruber, M. Gryaznevich, G. Giruzzi, S. Günter, N. Hayashi,
P. Helander, C. C. Hegna, D. F. Howell, D. A. Humphreys,
G. T. A. Huysmans, A. W. Hyatt, A. Isayama, S. C. Jardin,
Y. Kawano, A. Kellman, C. Kessel, H. R. Koslowski, R. J. La Haye,
E. Lazzaro, Y. Q. Liu, V. Lukash, J. Manickam, S. Medvedev,
V. Mertens, S. V. Mirnov, Y. Nakamura, G. Navratil, M. Okabayashi,
T. Ozeki, R. Paccagnella, G. Pautasso, F. Porcelli, V. D. Pustovitov,
V. Riccardo, M. Sato, O. Sauter, M. J. Schaffer, M. Shimada,
P. Sonato, E. J. Strait, M. Sugihara, M. Takechi, A. D. Turnbull,
E. Westerhof, D. G. Whyte, R. Yoshino, H. Zohm and ITPA
MHD, Disruption and Magnetic Control Topical Group:
Publications
125
Chapter 3: MHD stability, operational limits and disruptions.
Nuclear Fusion 47, S128-S202 (2007).
Henderson, M. A., S. Albert, P. Benin, T. Bonicelli, R. Chavan,
D. Campbell, S. Cirant, G. Dammertz, O. Dormicchi, O. Dumbrajs,
D. Fasel, T. P. Goodman, R. Heidinger, J.-P. Hogge, W. Kasparek,
C. Lievin, B. Piosczyk, E. Poli, G. Ramponi, G. Saibene, O. Sauter,
A. Serikov, G. Taddia, M. Thumm, M. Q. Tran, A. G. A. Verhoevenk
and H. Zohm: EU developments of the ITER ECRH system.
Fusion Engineering and Design 82, 454-462 (2007).
Herrmann, A.: Surface temperature measurement and heat
load estimation for carbon targets with plasma contact and
machine protection. Physica Scripta T128, 234-238 (2007).
Herrmann, A., A. Brendel, M. Balden and H. Bolt: Metal
Matrix Composite used as high-temperature heat sink material
for future fusion reactors. JEC Composite Magazine, 33,
67-70 (2007).
Herrmann, A., A. Kirk, A. Schmid, B. Koch, M. Laux, M. Maraschek,
H. W. Müller, J. Neuhauser, V. Rohde, M. Tsalas and E. Wolfrum:
The filamentary structure of ELMs in the scrape-off layer in
ASDEX Upgrade. Journal of Nuclear Materials 363-365,
528-533 (2007).
Hildebrandt, D. and A. Dübner: Thermal response of structural
and contaminated carbon surfaces to heat pulses.
Journal of Nuclear Materials 363-365, 1221-1225 (2007).
Hirai, T., H. Maier, M. Rubel, P. Mertens, R. Neu, E. Gauthier,
J. Likonen, C. Lungu, C. Maddaluno, G. Matthews, R. Mitteau,
O. Neubauer, G. Piazza, V. Philipps, B. Riccardi, C. Ruset,
I. Uytdenhouwen and JET-EFDA Contributors: R&D on full
tungsten divertor and beryllium wall for JET ITER-like Wall
Project. Fusion Engineering and Design 82, 1839-1845 (2007).
Hölzl, M., S. Günter, Q. Yu and K. Lackner: Numerical modeling
of diffusive heat transport across magnetic islands and highly
stochastic layers. Physics of Plasmas 14, 052501 (2007).
Homann, H., R. Grauer, A. Busse and W.-C. Müller:
Lagrangian statistics of Navier-Stokes and MHD Turbulence.
Journal of Plasma Physics 73, 6, 821-830 (2007).
Hopf, C., V. Rohde, W. Jacob, A. Herrmann, R. Neu, J. Roth
and ASDEX Upgrade Team: Oxygen glow discharge cleaning
in ASDEX Upgrade. Journal of Nuclear Materials 363-365,
882-887 (2007).
Hopf, C., M. Schlüter and W. Jacob: Chemical sputtering of
carbon films by argon ions and molecular oxygen at cryogenic
temperatures. Applied Physics Letters 90, 224106 (2007).

Hoshino, K., A. Hatayama, N. Asakura, H. Kawashima,
R. Schneider and D. Coster: Numerical analysis of the
SOL/divertor plasma flow with the effect of drifts. Journal
of Nuclear Materials 363-365, 539-543 (2007).
Huber, A., K. McCormick, P. Andrew, P. Beaumont, S. Dalley,
J. Fink, J. C. Fuchs, K. Fullard, W. Fundamenski, L. C. Ingesson,
F. Mast, A. Jachmich, G. F. Matthews, P. Mertens, V. Philipps,
R. A. Pitts, S. Sanders, W. Zeidner and JET-EFDA Contributors:
Upgraded bolometer system on JET for improved radiation measurements.
Fusion Engineering and Design 82, 1327-1334 (2007).
Huber, A., K. McCormick, P. Andrew, M. R. de Baar, P. Beaumont,
S. Dalley, J. Fink, J. C. Fuchs, K. Fullard, W. Fundamenski,
L. C. Ingesson, G. Kirnev, P. Lomas, F. Mast, S. Jachmich,
G. F. Matthews, P. Mertens, A. Meigs, V. Philipps, J. Rapp,
G. Saibene, S. Sanders, R. Sartori, M. F. Stamp, W. Zeidner
and JET-EFDA Contributors: Improved radiation measurements
on JET – First results from an upgraded bolometer system.
Journal of Nuclear Materials 363-365, 365-370 (2007).
Hynönen, V. and T. Kurki-Suonio: Erratum on Surface
Loads and Edge Fast Ion Distribution for Co- and Counterinjection
in ASDEX Upgrade. Plasma Physics and Controlled
Fusion 49, 1345-1347 (2007).
Hynönen, V., T. Kurki-Suonio, W. Suttrop, R. Dux, K. Sugiyama
and ASDEX Upgrade Team: Surface loads and edge fast ion
distribution for co- and counter-injection in ASDEX Upgrade.
Plasma Physics and Controlled Fusion 49, 151-174 (2007).
Igochine, V., O. Dumbrajs, H. Zohm, A. Flaws and ASDEX
Upgrade Team: Stochastic sawtooth reconnection in ASDEX
Upgrade. Nuclear Fusion 47, 23-32 (2007).
Jachmich, S., T. Eich, W. Fundamenski, A. Kallenbach, R. A. Pitts
and JET-EFDA Contributors: Divertor particle and power
deposition profiles in JET ELMY H-mode discharges.
Journal of Nuclear Materials 363-365, 1050-1055 (2007).
Jacob, W. and J. Roth: Chemical Sputtering. Sputtering by
Particle Bombardment: Experiments and Computer Calculations
from Threshold to MeV Energies. (Eds.) R. Behrisch,
W. Eckstein. Topics in Applied Physics 110. Springer Verlag,
Berlin, 329-400 (2007).
Jolliet, S., A. Bottino, P. Angelino, R. Hatzky, T. M. Tran,
B. F. Mcmillan, O. Sauter, K. Appert, Y. Idomura and L. Villard:
A global collisionless PIC code in magnetic coordinates.
Computer Physics Communications 177, 409-425 (2007).
Joseph, I., R. A. Moyer, T. E. Evans, M. J. Schaffer, A. M. Runov,
R. Schneider, S. V. Kasilov, M. Groth and M. E. Fenstermacher:
Publications
126
Stochastic transport modeling of resonant magnetic perturbations
in DIII-D. Journal of Nuclear Materials 363-365,
591-595 (2007).
Kallenbach, A., R. Dux, J. Harhausen, C. F. Maggi, R. Neu,
T. Pütterich, V. Rohde, K. Schmid, E. Wolfrum and ASDEX
Upgrade Team: Spectroscopic investigation of carbon
migration with tungsten walls in ASDEX Upgrade. Journal
of Nuclear Materials 363-365, 60-65 (2007).
Kamiya, K., N. Asakura, J. Boedo, T. Eich, G. Federici,
M. Fenstermacher, K. Finken, A. Herrmann, J. Terry, A. Kirk,
B. Koch, A. N. Loarte, R. Maingi, R. Maqueda, E. Nardon,
N. Oyama and R. Sartori: Edge localized modes: recent
experimental findings and related issues. Plasma Physics
and Controlled Fusion 49, S43-S62 (2007).
Kasparek, W., M. Petelin, V. Erckmann, D. Shchegolkov,
A. Bruschi, S. Cirant, A. Litvak, M. Thumm, B. Plaum,
M. Grünert, M. Malthaner, ECRH Groups at IPP Greifswald,
FZK Karlsruhe and IPF Stuttgart: Fast switching and
power combination of high-power electron cyclotron wave
beams: principles, numerical results and experiments. Fusion
Science and Technology 52, 281-290 (2007).
Kaufmann, M. and R. Neu: Tungsten as first wall material in
fusion devices. Invited. Fusion Engineering and Design 82,
521-527 (2007).
Kessel, C. E., G. Giruzzi, A. C. C. Sips, R. V. Budny, J. F. Artaud,
V. Basiuk, F. Imbeaux, E. Joffrin, M. Schneider, M. Murakami,
T. Luce, H. St John, T. Oikawa, N. Hayashi, T. Takizuka, T. Ozeki,
Y.-S. Na, J. M. Park, J. Garcia and A. A. Tucillo: Simulation
of the hybrid and steady state advanced operating modes in
ITER. Nuclear Fusion 47, 1274-1284 (2007).
Kizu, K., K. Tsuchiya, T. Ando, C. Sborchia, K. Masaki, S. Sakurai,
A. M. Sukegawa, H. Tamai, T. Fujita, M. Matsukawa, Y. Miura
and M. Kikuchi: Conceptual Design of Magnet System for
JT-60 Super Advanced (JT-60SA). IEEE Transactions on
Applied Superconductivity 17, 1348-1352 (2007).
Kobayashi, M., Y. Feng, A. Loarte, G. Federici, G. Strohmayer,
M. Shimada, F. Sardei, D. Reiter and M. Sugihara: 3D
edge transport analysis of ITER start-up configuration for
limiter power load assessment. Nuclear Fusion 47, 61-73
(2007).
Kobayashi, M., Y. Feng, S. Masuzaki, M. Shoji, J. Miyazawa,
T. Morisaki, N. Oyabu, N. Ashikawa, A. Komori, O. Motojima,
LHD Experimental Group, Y. Igitkhanov, F. Sardei and
D. Reiter: Divertor transport study in the large helical device.
Journal of Nuclear Materials 363-365, 294-300 (2007).

Kobayashi, M., N. Ohyabu, T. Mutoh, R. Kumazawa, Y. Feng,
M. Shoji, T. Morisaki, S. Masuzaki, A. Sagara, R. Sakamoto,
T. Seki, J. Miyazawa, T. Watanabe, M. Goto, K. Ikeda,
H. Kasahara, S. Morita, B.J. Peterson, N. Ashikawa, K. Saito,
S. Sakakibara, T. Tokuzawa, Y. Nakamura, K. Narihara, L. Yamada,
H. Yamada, A. Komori, O. Motojima and LHD Experimental
Group: Edge transport control with the local island divertor and
recent progress in LHD. Fusion Science and Technology 52,
566-573 (2007).
Koch, B., A. Herrmann, A. Kirk, H. Meyer, J. Dowling,
J. Harhausen, J. Neuhauser, H. W. Müller, W. Bohmeyer,
G. Fußmann, AUG Team and MAST Team: Observation of
ELM structures in MAST and AUG using a fast camera.
Journal of Nuclear Materials 363-365, 1056-1060 (2007).
Koch, F. and H. Bolt: Self Passivating W-based Alloys as
Plasma Facing Materials for Nuclear Fusion. Physica
Scripta T128, 100-105 (2007).
Koch, F., R. Nocentini, B. Heinemann, S. Lindig, P. Junghanns
and H. Bolt: MoS2 coatings for the narrow support elements
of the W-7X non planar coils. Fusion Engineering and
Design 82, 1614-1620 (2007).
Kocsis, G., S. Kalvin, P. T. Lang, M. Maraschek, J. Neuhauser,
W. Schneider, T. Szepesi and ASDEX Upgrade Team: Spatiotemporal
investigations on the triggering of pellet induced
ELMs. Nuclear Fusion 47, 1166-1175 (2007).
Köck, T., A. Brendel and H. Bolt: Interface reactions between
silicon carbide and interlayers in silicon carbide-copper
metal-matrix composites. Journal of Nuclear Materials 362,
197-201 (2007).
Köppen, M. and J. Kißlinger: Simulation of Voltage and
Current Development in the Wendelstein 7-X Coil System
Taking into Account Fault Conditions. Fusion Engineering
and Design 82, 1549-1554 (2007).
Kolesnichenko, Y., V. Lutsenko, V. S. Marchenko, A. Weller,
R. B. White, Y. V. Yakovenko and K. Yamazaki: Magnetohydrodynamic
activity and energetic ions in fusion plasmas.
Plasma Physics and Controlled Fusion 49, A159-A166 (2007).
Kolesnichenko, Ya. I., V. V. Lutsenko, A. Weller, A. Werner,
Yu. V. Yakovenko, J. Geiger and O. P. Fesenyuk: Conventional
and non-conventional global Alfvén eigenmodes in
stellarators. Physics of Plasmas 14, 102504 (2007).
Kolev, S., S. Lishev, A. Shivarova, K. Tarnev and R. Wilhelm:
Magnetic filter operation in hydrogen plasmas. Plasma
Physics and Controlled Fusion 49, 1349-1369 (2007).
Publications
127
Kraus, W., P. McNeely, M. Berger, S. Christ-Koch, H. D. Falter,
U. Fantz, P. Franzen, M. Fröschle, B. Heinemann, S. Leyer,
R. Riedl, E. Speth and D. Wünderlich: RF Negative Ion
Source Development at IPP Garching. Production and Neutralization
of Negative Ions and Beams. (Ed.) M. P. Stockli.
AIP Conference Proceedings 925. American Institute of
Physics, Melville, NY, 224-237 (2007).
Kreter, A., A. Kirschner, P. Wienhold, J. Likonen, M. Mayer,
V. Philipps, U. Samm and TEXTOR Team: Long-Term
Erosion and Deposition Studies of the Main Graphite
Limiter in TEXTOR. Physica Scripta T128, 35-39 (2007).
Krieger, K., W. Jacob, D. Rudakov, R. Bastasz, G. Federici,
A. Litnovsky, H. Maier, V. Rohde, G. Strohmayer, W. West,
J. Whaley, C. Wong, ASDEX Upgrade Team and DIII-D Teams:
Formation of deuterium-carbon inventories in gaps of plasma
facing components. Journal of Nuclear Materials 363-365,
870-876 (2007).
Kukushkin, A. S., H. D. Pacher, V. Kotov, D. Reiter, D. Coster
and G. W. Pacher: Effect of conditions for gas recirculation
on divertor operation in ITER. Nuclear Fusion 47, 698-705
(2007).
Kukushkin, A. S., H. D. Pacher, V. Kotov, D. Reiter, D. P. Coster
and G. W. Pacher: Effect of the dome on divertor performance
in ITER. Journal of Nuclear Materials 363-365,
308-313 (2007).
Kurzan, B., L. D. Horton, H. D. Murmann, J. Neuhauser,
W. Suttrop and ASDEX Upgrade Team: Thomson scattering
analysis of large scale fluctuations in the ASDEX Upgrade
edge. Plasma Physics and Controlled Fusion 49, 825-844
(2007).
Lang, P., P. Cierpka, J. Harhausen, J. Neuhauser, C. Wittmann,
ASDEX Upgrade Team, K. Gal, S. Kalvin, G. Kocsis, J. Sarkozi,
T. Szepesi, C. Dorner and G. Kauke: Cryogenic pellet launcher
adapted for controlling of tokamak plasma edge instabilities.
Review of Scientific Instruments 78, 023504 (2007).
Lang, P. T., B. Alper, R. Buttery, K. Gal, J. Hobirk, J. Neuhauser,
M. Stamp and JET EFDA Contributors: ELM triggering by
local pellet perturbations in type-I ELMy H-mode plasma at
JET. Nuclear Fusion 47, 754-761 (2007).
Lang, P. T., P. Cierpka, J. Harhausen, M. Kaufmann, J. Neuhauser,
C. Wittmann, G. Kocsis, J. Sárközi, T. Szepesi, C. Dorner,
G. Kauke and ASDEX Upgrade Team: A pellet launcher tool
optimized for the control of edge localized modes in ASDEX
Upgrade H-mode plasmas. Fusion Engineering and Design 82,
1073-1080 (2007).

Laqua, H., J. Schacht and A. Spring: Runtime resource
checking at Wendelstein 7-X during plasma operation. Fusion
Engineering and Design 82, 982-987 (2007).
Laqua, H. P.: Electron Bernstein Wave Heating and Diagnostic
(Review article). Plasma Physics and Controlled Fusion 49,
R1-R42 (2007).
Lauber, P., S. Günter, A. Könies and S. D. Pinches: LIGKA:
A linear gyrokinetic code for the description of background
kinetic and fast particle effects on the MHD stability in
tokamaks. Journal of Computational Physics 226, 447-465
(2007).
Lazaros, A., M. Maraschek and H. Zohm: A model for the
advantage of early electron cyclotron current drive in the suppression
of neoclassical tearing modes. Physics of Plasmas 14,
042505 (2007).
Levchuk, D.: Plasma assisted techniques for deposition of
superhard nanocomposite coatings. Surface and Coatings
Technology 201, 6071-6077 (2007).
Levchuk, D., S. Levchuk, H. Maier, H. Bolt and A. Suzuki:
Erbium oxide as a new promising tritium permeation barrier.
Journal of Nuclear Materials 367-370, 1033-1037 (2007).
Levchuk, S., S. Lindig, A. Brendel and H. Bolt: Interface
reactions and control of diffusion at the interface between
SiC fibres and layer of deposited Fe-9Cr base alloy. Journal
of Nuclear Materials 367-370, 1233-1237 (2007).
Liang, Y., H. R. Koslowski, P. R. Thomas, E. Nardon, S. Jachmich,
B. Alper, P. Andrew, Y. Andrew, G. Arnoux, Y. Baranov,
M. Becoulet, M. Beurskens, T. Biewer, M. Bigi, K. Crombe,
E. De La Luna, P. de Vries, T. Eich, H. G. Esser, W. Fundamenski,
S. Gerasimov, C. Giroud, M. P. Gryaznevich, D. Harting,
N. Hawkes, S. Hotchin, D. Howell, A. Huber, M. Jakubowski,
V. Kiptily, A. Kreter, L. Moreira, V. Parail, S. D. Pinches,
E. Rachlew, O. Schmitz, O. Zimmermann and JET EFDA
Contributors: Active control of type-I edge localized modes on
JET. Invited Paper. Plasma Physics and Controlled Fusion 49,
B581-B589 (2007).
Liang, J. H., M. Mayer, J. Roth, M. Balden and W. Eckstein:
Hydrogen isotopic effects on the chemical erosion of graphite
induced by ion irradiation. Journal of Nuclear Materials
363-365, 184-189 (2007).
Linsmeier, C., K. Ertl, J. Roth, A. Wiltner, K. Schmid, F. Kost,
S. Bhattacharyya, M. Baldwin and R. Doerner: Binary
beryllium-tungsten mixed materials. Journal of Nuclear
Materials 363-365, 1129-1137 (2007).
Publications
128
Lipschultz, B., X. Bonnin, G. Counsell, A. Kallenbach,
A. Kukushkin, K. Krieger, A. Leonard, A. Loarte, R. Neu,
A. Pitts, T. Rognlien, J. Roth, C. Skinner, J. L. Terry, E. Tsitrone,
D. Whyte, S. Zweben, N. Asakura, D. Coster, R. Doerner, R. Dux,
G. Federici, M. Fenstermacher, W. Fundamenski, P. Ghendri,
A. Herrmann, J. Hu, S. Krasheninnikov, G. Kirnev, A. Kreter,
V. Kurnaev, B. LaBombard, S. Lisgo, T. Nakano, N. Ohno,
H. D. Pacher, J. Paley, Y. Pan, G. Pautasso, V. Philipps, V. Rohde,
D. Rudakov, P. Stangeby, S. Takamura, T. Tanabe, Y. Yang
and S. Zhu: Plasma-surface interaction, scrape-off layer and
divertor physics: implications for ITER. Nuclear Fusion 47,
1189-1205 (2007).
Litaudon, X., G. Arnoux, M. Beurskens, S. Brezinsek, C. D. Challis,
F. Crisanti, P. C. De Vries, C. Giroud, R. A. Pitts, F. G. Rimini,
Y. Andrew, Y. F. Baranov, M. Brix, P. Buratti, R. Cesario,
Y. Corre, E. De La Luna, W. Fundamenski, E. Giovannozzi,
M. P. Gryaznevich, N. C. Hawkes, J. Hobirk, A. Huber,
S. Jachmich, E. Joffrin, H. R. Koslowski, Y. Liang, T. Loarer,
P. Lomas, T. Luce, J. Mailloux, G. F. Matthews, K. McCormick,
D. Mazon, D. Moreau, V. Pericoli, V. Philipps, E. Rachlew,
S. D. A. Reyes-Cortes, G. Saibene, S. E. Sharapov, I. Voitsekovitch,
L. Zabeo, O. Zimmermann, K. D. Zatrow and JET-EFDA
Contributors: Development of steady-state scenarios compatible
with ITER-like wall conditions. Invited Paper. Plasma
Physics and Controlled Fusion 49, B529-B550 (2007).
Litnovsky, A., V. Philipps, A. Kirschner, P. Wienhold,
G. Sergienko, A. Kreter, U. Samm, O. Schmitz, K. Krieger,
P. Karduck, M. Blome, B. Emmoth, M. Rubel, U. Breuer and
A. Scholl: Carbon transport, deposition and fuel accumulation
in castellated structures exposed in TEXTOR. Journal
of Nuclear Materials 367-370, 1481-1486 (2007).
Litnovsky, A., V. Philipps, P. Wienhold, K. Krieger, G. Sergienko,
A. Kreter, O. Schmitz, U. Samm, P. Mertens, A. Kirschner,
S. Droste, S. Richter, U. Breuer, A. Scholl, A. Besmehn and
Y. Xu: Castellated structures for ITER: the influence of the
shape of castellation on the impurity deposition and fuel
accumulation in gaps. Physica Scripta T128, 45-49 (2007).
Loarer, T., C. Brosset, J. Bucalossi, P. Coad, G. Esser, J. Hogan,
J. Likonen, M. Mayer, P. Morgan, V. Philipps, V. Rohde, J. Roth,
M. Rubel, E. Tsitrone, A. Widdowson and JET EFDA Contributors:
Gas balance and fuel retention in fusion devices.
Nuclear Fusion 47, 1112-1120 (2007).
Loarte, A., B. Lipschultz, A. S. Kukushkin, G. F. Matthews,
P. C. Stangeby, N. Asakura, G. F. Counsell, G. Federici,
A. Kallenbach, K. Krieger, A. Mahdavi, V. Philipps, D. Reiter,
J. Roth, J. Strachan, D. Whyte, R. Doerner, T. Eich, W. Fundamenski,
A. Herrmann, M. Fenstermacher, P. Ghendrih, M. Groth,
A. Kirschner, S. Konoshima, B. LaBombard, P. Lang, A. W. Leonard,

P. Monier-Garbet, R. Neu, H. Pacher, B. Pegourie, R. A. Pitts,
S. Takamura, J. Terry, E. Tsitrone and ITPA Scrape-off Layer
and Divertor Physics Topical Group: Chapter 4: Power and
particle control. Nuclear Fusion 47, S203-S263 (2007).
Loarte, A., G. Saibene, R. Sartori, V. Riccardo, P. Andrew, J. Paley,
W. Fundamenski, T. Eich, A. Herrmann, G. Pautasso, A. Kirk,
G. Counsell, G. Federici, G. Strohmayer, D. Whyte, A. Leonard,
R. A. Pitts, I. Landmann, B. Bazylev and S. Pestchanyi: Transient
Heat Loads in Current Fusion Experiments, Extrapolation
to ITER and Consequences for its Operation. Physica
Scripta T128, 222-228 (2007).
Lundwall, M., W. Pokapanich, H. Bergersen, A. Lindblad,
T. Rander, G. Öhrwall, M. Tchaplyguine, S. Barth, U. Hergenhahn,
S. Svensson and O. Björneholm: Self-assembled heterogeneous
argon/neon core-shell clusters studied by photoelectron
spectroscopy. Journal of Chemical Physics 126, 214706 (2007).
Lunt, T., C. Silva, H. Fernandes, C. Hidalgo, M. A. Pedrosa,
P. Duarte, H. Figueiredo and T. Pereira: Edge plasma pressure
measurements using a mechanical force sensor on the
tokamak ISTTOK. Plasma Physics and Controlled Fusion 49,
1783-1790 (2007).
Lyssoivan, A., R. Koch, D. Van Eester, G. Van Wassenhov,
M. Vervier, R. Weynants, M. Freisinger, A. Kreter, V. Philipps,
H. Reimer, U. Samm, G. Sergienko, V. Bobkov, H.-U. Fahrbach,
D. Hartmann, A. Herrmann, J.-M. Noterdaeme, V. Rohde,
W. Suttrop, E. Gauthier, E. de la Cal, TEXTOR Team and
ASDEX Upgrade Team: New scenarios of ICRF wall conditioning
in TEXTOR and ASDEX Upgrade. Journal of
Nuclear Materials 363-365, 1358-1363 (2007).
Maggi, C. F., R. J. Groebner, N. Oyama, R. Sartori, L. Horton,
A. C. C. Sips, W. Suttrop, ASDEX Upgrade Team, A. Leonard,
T. C. Luce, M. R. Wade, DIII-D Team, Y. Kamada, H. Urano,
JT-60U Team, Y. Andrew, C. Giroud, E. Joffrin, E. de la Luna
and EFDA JET Contributors for the Pedestal and Edge Physics
and the Stead State Operation Topical Groups of the ITPA:
Characteristics of H-mode pedestal in improved confinement
scenarios in ASDEX Upgrade, DIII-D, JET and JT-60U.
Nuclear Fusion 47, 535-551 (2007).
Mahdizadeh, N., F. Greiner, T. Happel, A. Kendl, M. Ramisch,
B. D. Scott and U. Stroth: Investigation of the parallel dynamics
of drift-wave turbulence in toroidal plasmas. Plasma
Physics and Controlled Fusion 49, 1005-1017 (2007).
Maier, H., T. Hirai, M. Rubel, R. Neu, P. Mertens, H. Greuner,
C. Hopf, G. Matthews, O. Neubauer, G. Piazza, E. Gauthier,
J. Likonen, R. Mitteau, G. Maddaluno, B. Riccardi, V. Philipps,
C. Ruset, C. Lungu and JET EFDA Contributors: Tungsten
Publications
129
and Beryllium Armour Development for the JET ITER-like
Wall Project. Nuclear Fusion 47, 222-227 (2007).
Maier, H., R. Neu, H. Greuner, C. Hopf, G. Matthews, G. Piazza,
T. Hirai, G. Counsell, X. Courtois, R. Mitteau, E. Gauthier,
J. Likonen, G. Maddaluno, V. Philipps, B. Riccardi, C. Ruset and
EFDA-JET Team: Tungsten Coatings for the JET ITER-like
Wall Project. Journal of Nuclear Materials 363-365, 1246-
1250 (2007).
Manini, A., J. Berrino, S. Cirant, G. D’Antona, F. Gandini,
G. Grünwald, F. Leuterer, M. Maraschek, F. Monaco, G. Neu,
G. Raupp, D. Sormani, J. Stober, W. Suttrop, W. Treutterer,
D. Wagner, H. Zohm and ASDEX Upgrade Team: Development
of a feedback system to control MHD instabilities in ASDEX
Upgrade. Fusion Engineering and Design 82, 995-1001 (2007).
Maraschek, M., G. Gantenbein, Q. Yu, H. Zohm, S. Günter,
F. Leuterer, A. Manini, ECHR Group and ASDEX Upgrade
Team: Enhancement of the Stabilization Efficiency of a Neoclassical
Magnetic Island by Modulated Electron Cyclotron
Current Drive in the ASDEX Upgrade Tokamak. Physical
Review Letters 98, 025005 (2007).
Marcuzzi, D., P. Agostinetti, M. Dalla Palma, H. D. Falter,
B. Heinemann and R. Riedl: Design of the RF ion source for the
ITER NBI. Fusion Engineering and Design 82, 798-805 (2007).
Marki, J., R. A. Pitts, T. Eich, A. Herrmann, J. Horacek,
F. Sanchez and G. Veres: Sheath heat transmission factors on
TCV. Journal of Nuclear Materials 363-365, 382-388 (2007).
Markin, S. N., D. Primetzhofer, J. E. Valdes, E. Taglauer and
P. Bauer: Neutralization of low energy He + ions by Cu in the
auger regime. Nuclear Instruments and Methods in Physics
Research B: Beam Interactions with Materials and Atoms 258,
18-20 (2007).
Marushchenko, N. B., V. Erckmann, H. J. Hartfuß, M. Hirsch,
H. P. Laqua, H. Maaßberg and Y. Turkin: Ray Tracing Simulations
of ECR Heating and ECE Diagnostic at W7-X Stellarator.
Plasma and Fusion Research 2, S1129 (2007).
Matthews, G., P. Edwards, T. Hirai, M. Kear, A. Lioure, P. Lomas,
A. Loving, C. Lungu, H. Maier, P. Mertens, D. Neilson, J. Pamela,
V. Philipps, G. Piazza, V. Riccardo, M. Rubel, C. Ruset, E. Villedieu,
M. Way and ITER-Like Wall Project Team: Overview of the
ITER-like Wall Project. Physica Scripta T128, 137-143 (2007).
Matyash, K., R. Schneider, K. Dittmann, J. Meichsner, F. X. Bronold
and D. Tskhakaya: Radio-frequency discharges in oxygen: III.
Comparison of modelling and experiment. Journal of
Physics D 40, 6601-6607 (2007).

Matyash, K., R. Schneider, F. Taccogna, A. Hattayama,
S. Longo, M. Capitelli, D. Tskhakaya and F. X. Bronold:
Particle in Cell Simulation of Low Temperature Laboratory
Plasma. Contributions to Plasma Physics 47, 595-634 (2007).
Matyash, K., R. Schneider, F. Taccogna and D. Tskhakaya:
Finite size effect of dust charging in the magnetized edge plasma.
Journal of Nuclear Materials 363-365, 458-461 (2007).
Mayer, M., J. Likonen, J. P. Coad, H. Maier, M. Balden,
S. Lindig, E. Vainonen-Ahlgren, V. Philipps and JET-EFDA
Contributors: Tungsten erosion in the outer divertor of JET.
Journal of Nuclear Materials 363-365, 101-106 (2007).
Mayer, M., V. Rohde, G. Ramos, E. Vainonen-Ahlgren,
J. Likonen, J. Chen and ASDEX Upgrade Team: Erosion of
Tungsten and Carbon Markers in the Outer Divertor of
ASDEX-Upgrade. Physica Scripta T128, 106-110 (2007).
Mayer, M., V. Rohde, G. Ramos, E. Vainonen-Ahlgren,
J. Likonen, A. Herrmann, R. Neu and ASDEX Upgrade Team:
The Deuterium Inventory in ASDEX Upgrade. Nuclear
Fusion 47, 1607-1617 (2007).
McCormick, K., P. Grigull, H. Ehmler, E. Pasch, NBI Team,
ECRH Team and W7-AS Team: A new edge-based energy
scaling law for W7-AS and its implications for boundaryisland
divertor operation. Journal of Nuclear Materials 363-365,
389-394 (2007).
McDonald, D. C., J. G. Cordey, K. Thomsen, O. J. W. F. Kardaun,
J. A. Snipes, M. Greenwald, L. Sugiyama, F. Ryter, A. Kus,
J. Stober, J. C. DeBoo, C. C. Petty, G. Bracco, M. Romanelli,
Z. Cui, Y. Liu, Y. Miura, K. Shinohara, K. Tsuzuki, Y. Kamada,
T. Takizuka, H. Urano, M. Valovic, R. Akers, C. Brickley, A. Sykes,
M. J. Walsh, S. M. Kaye, C. Bush, D. Hogewei, Y. R. Martin,
A. Cote, G. Pacher, J. Ongena, F. Imbeaux, G. T. Hoang,
S. Lebedev, A. Chudnovskiy and V. Leonov: Recent progress
on the development and analysis of the ITPA global H-mode
confinement database. Nuclear Fusion 47, 147-174 (2007).
Menmuir, S., E. Rachlew, U. Fantz, R. Pugno, R. Dux and
ASDEX Upgrade Team: Molecular contribution to the Dα emission
in the divertor of the ASDEX Upgrade experiment. Journal
of Quantitative Spectroscopy and Radiative Transfer 105,
425-437 (2007).
Meyer-Spasche, R.: On difference schemes for quasilinear
evolution problems. Electronic Transactions on Numerical
Analysis 27, 78-93 (2007).
Mikkelsen, D. R., H. Maaßberg, M. C. Zarnstorff, C. D. Beidler,
W. A. Houlberg, W. Kernbichler, H. Mynick, D. A. Spong,
Publications
130
P. Strand and V. Tribaldos: Assessment of Transport in
NCSX. Fusion Science and Technology 51, 166-180 (2007).
Milch, I.: Sonnenfeuer im Labor. Wo steht die Fusionsforschung?
Kultur und Technik – das Magazin aus dem
Deutschen Museum 31, 2, 46-51 (2007).
Mishchenko, A., P. Helander and Y. Turkin: Curvature Particle
Pinch in Tokamak and Stellarator Geometry. Physics of
Plasmas 14, 102308 (2007).
Mishchenko, A. and A. Könies: A many-particle approach to
the gyro-kinetic theory. Journal of Plasma Physics 73, 757-772
(2007).
Missirlian, M., A. Durocher, A. Grosman, J. Schlosser, J. Boscary,
F. Escourbiac and F. Cismondi: Qualification of high heat
flux components: application to target elements of W7-X
divertor. Physica Scripta T128, 182-188 (2007).
Missirlian, M., H. Traxler, J. Boscary, A. Durocher, F. Escourbiac,
J. Schlosser, B. Schedler and P. Schuler: Infrared thermography
inspection methods applied to the target elements of W7-X
divertor. Fusion Engineering and Design 82, 1747-1755 (2007).
Mitteau, R., J. M. Missiaen, P. Brustolin, O. Ozer, A. Durocher,
C. Ruset, C. P. Lungu, X. Courtois, C. Dominicy, H. Maier,
C. Grisolia, G. Piazza and P. Chappuis: Recent developments
toward the use of tungsten as armour material in plasma
facing components. Fusion Engineering and Design 82,
1700-1705 (2007).
Mueck, A., Y. Camenen, S. Coda, L. Curchod, T. P. Goodman,
H. P. Laqua, A. Pochelon, L. Porte, V. S. Udintsev, F. Volpe
and TCV Team: Electron Bernstein Wave Heating and Emission
in the TCV Tokamak. Fusion Science and Technology 52,
221-229 (2007).
Mueck, A., L. Curchod, Y. Camenen, S. Coda, T. P. Goodman,
H. P. Laqua, A. Pochelon, L. Porte and F. Volpe: Demonstration
of Electron-Bernstein-Wave Heating in a Tokamak
via O-X-B Double-Mode Conversion. Physical Review
Letters 98, 175004 (2007).
Müller, H. W., V. Bobkov, A. Herrmann, M. Maraschek,
J. Neuhauser, V. Rohde, A. Schmid, M. Tsalas and ASDEX
Upgrade Team: Deuterium plasma flow in the scrape-off-layer
of ASDEX Upgrade. Journal of Nuclear Materials 363-365,
605-610 (2007).
Müller, W.-C. and A. Busse: Diffusion and dispersion of passive
tracers: Navier-Stokes vs. MHD turbulence. Europhysics
Letters 78, 14003 (2007).

Müller, W.-C. and M. Thiele: Scaling and energy transfer in
rotating turbulence. Europhysics Letters 77, 34003 (2007).
Mukhovatov, V., M. Shimada, K. Lackner, D. J. Campbell,
N. A. Uckan, J. C. Wesley, T. C. Hender, B. Lipschultz, A. Loarte,
R. D. Stambaugh, R. J. Goldston, Y. Shimomura, M. Fujiwara,
M. Nagami, V. D. Pustovitov, H. Zohm, ITPA CC Members,
ITPA Topical Group Chairs and Co-Chairs and ITER International
Team: Chapter 9: ITER contributions for Demo
plasma development. Nuclear Fusion 47, S404-S413 (2007).
Murakami, S., H. Yamada, A. Wakasa, H. Inagaki, K. Tanaka,
K. Narihara, S. Kubo, T. Shimozuma, H. Funaba, J. Miyazawa,
S. Morita, K. Ida, K. Y. Watanabe, M. Yokoyama, H. Maaßberg,
C. D. Beidler and LHD Experimental Group: Effect of Neoclassical
Transport Optimization on Electron Heat Transport
in the Low-collisionality LHD Plasma. Fusion Science and
Technology 51, 112-121 (2007).
Murari, A., T. Edlington, J. Brzozowski, E. de la Luna, P. Andrew,
G. Arnoux, F. E. Cecil, L. Cupido, D. Darrow, V. Kiptily,
J. Fessey, E. Gauthier, S. Hacquin, K. Hill, A. Huber, T. Loarer,
K. McCormick, M. Reich and JET-EFDA Contributors: JET
new diagnostic capability on the route to ITER. Fusion
Engineering and Design 82, 1161-1166 (2007).
Nakamura, K., H. Iguchi, J. Schweinzer, A. Shimizu, M. Isobe,
D. Takahashi, S. Nishimura, C. Suzuki, Y. Yoshimura, K. Nagaoka,
T. Minami, T. Akiyama, K. Ida, K. Matsuoka and S. Okamura:
Two-dimensional plasma structure in the edge region of the
compact helical system. Nuclear Fusion 47, 251-256 (2007).
Neu, G., K. Engelhardt, G. Raupp, W. Treutterer, D. Zasche,
T. Zehetbauer and ASDEX Upgrade Team: The ASDEX
Upgrade Discharge Schedule. Fusion Engineering and
Design 82, 1111-1116 (2007).
Neu, R., M. Balden, V. Bobkov, R. Dux, O. Gruber, A. Herrmann,
A. Kallenbach, M. Kaufmann, C. F. Maggi, H. Maier, H. W. Müller,
T. Pütterich, R. Pugno, V. Rohde, A. C. C. Sips, J. Stober,
W. Suttrop, C. Angioni, C. V. Atanasiu, W. Becker, K. Behler,
K. Behringer, A. Bergmann, T. Bertoncelli, R. Bilato, A. Bottino,
M. Brambilla, F. Braun, A. Buhler, A. Chankin, G. Conway,
D. P. Coster, P. de Marne, S. Dietrich, K. Dimova, R. Drube,
T. Eich, K. Engelhardt, H.-U. Fahrbach, U. Fantz, L. Fattorini,
J. Fink, R. Fischer, A. Flaws, P. Franzen, J. C. Fuchs, K. Gal,
M. Garcia Munoz, M. Gemisic-Adamov, L. Giannone, S. Gori,
S. da Graca, H. Greuner, A. Gude, S. Günter, G. Haas,
J. Harhausen, B. Heinemann, N. Hicks, J. Hobirk, D. Holtum,
C. Hopf, L. Horton, M. Huart, V. Igochine, S. Kalvin, O. Kardaun,
M. Kick, G. Kocsis, H. Kollotzek, C. Konz, K. Krieger,
T. Kurki-Suonio, B. Kurzan, K. Lackner, P. T. Lang, P. Lauber,
M. Laux, J. Likonen, L. Liu, A. Lohs, K. Mank, A. Manini,
Publications
131
M.-E. Manso, M. Maraschek, P. Martin, Y. Martin, M. Mayer,
P. McCarthy, K. McCormick, H. Meister, F. Meo, P. Merkel,
R. Merkel, V. Mertens, F. Merz, H. Meyer, M. Mlyneck,
F. Monaco, H. Murmann, G. Neu, J. Neuhauser, B. Nold,
J.-M. Noterdaeme, G. Pautasso, G. Pereverzev, E. Poli,
M. Püschel, G. Raupp, M. Reich, B. Reiter, T. Ribeiro, R. Riedl,
J. Roth, M. Rott, F. Ryter, W. Sandmann, J. Santos, K. Sassenberg,
A. Scarabosio, G. Schall, J. Schirmer, A. Schmid, W. Schneider,
G. Schramm, R. Schrittwieser, W. Schustereder, J. Schweinzer,
S. Schweizer, B. Scott, U. Seidel, F. Serra, M. Sertoli, A. Sigalov,
A. Silva, E. Speth, A. Stäbler, K.-H. Steuer, E. Strumberger,
G. Tardini, C. Tichmann, W. Treutterer, C. Tröster, L. Urso,
E. Vainonen-Ahlgren, P. Varela, L. Vermare, D. Wagner,
M. Wischmeier, E. Wolfrum, E. Würsching, D. Yadikin, Q. Yu,
D. Zasche, T. Zehetbauer, M. Zilker and H. Zohm: Plasma
wall interaction and its implication in an all tungsten divertor
tokamak. Invited Paper. Plasma Physics and Controlled
Fusion 49, B59-B70 (2007).
Neu, R., V. Bobkov, R. Dux, A. Kallenbach, T. Pütterich,
H. Greuner, O. Gruber, A. Herrmann, C. Hopf, K. Krieger,
C. F. Maggi, H. Maier, M. Mayer, V. Rohde, K. Schmid, W. Suttrop
and ASDEX Upgrade Team: Final steps to an all tungsten
divertor tokamak. Journal of Nuclear Materials 363-365, 52-59
(2007).
Neu, R., H. Maier, E. Gauthier, H. Greuner, T. Hirai, C. Hopf,
J. Likonen, G. Maddaluno, F. Matthews, R. Mitteau, V. Philipps,
G. Piazza, C. Ruset and JET EFDA Contributors: Investigation
of Tungsten Coatings on Graphite and CFC. Physica
Scripta T128, 150-156 (2007).
Neu, R., T. Pütterich, R. Dux, A. Pospieszczyk, A. Sergienko
and ASDEX Upgrade Team: Tungsten Spectroscopy for Fusion
Plasmas. Atomic and Molecular Data and their Applications:
5 th International Conference on Atomic and Molecular
Data and Their Applications (ICAMDATA). (Ed.) E. Roueff.
AIP Conference Proceedings 901. American Institute of
Physics, Melville, NY, 85-94 (2007).
Nevins, W. M., S. E. Parker, Y. Chen, J. Candy, A. Dimits,
W. Dorland, G. W. Hammett and F. Jenko: Verification of
gyrokinetic δf simulations of electron temperature gradient
turbulence. Physics of Plasmas 14, 062301 (2007).
Newton, S. L., P. Helander and P. J. Catto: Collisional bulk
ion transport and poloidal rotation driven by neutral beam
injection. Physics of Plasmas 14, 062301 (2007).
Nieckchen, P. and P. Batistoni: Imbrigliare l’energia delle
stelle. ENEA – Dipartimento Fusione, Tecnologie e Presdio
Nucleari Associazione EURATOM-ENEA, Frascati, 20 p.
(2007).

Nieckchen, P. and P. Batistoni: Sulla strada della fusione –
Opportunità per l’industria italiana. ENEA – Dipartimento Fusione,
Tecnologie e Presdio Nucleari Associazione EURATOM-
ENEA, Frascati, 16 p. (2007).
Omar, B., A. Wierling, S. Günter and G. Röpke: Hydrogen
Balmer Spectrum from a High-Pressure Arc Discharge:
Revisited. Contributions to Plasma Physics 47, 315-323
(2007).
Orsitto, F. P., J. M. Noterdaeme, A. E. Costley, A. J. H. Donné
and ITPA TG on Diagnostics: Requirements for fast particle
measurements on ITER and candidate measurement techniques.
Nuclear Fusion 47, 1311-1317 (2007).
Osiac, M., T. Schwarz-Selinger, D. O’Connell, B. Heil, Z. L. Petrovic,
M. M. Turner, T. Gans and U. Czarnetzki: Plasma Boundary
Sheath in the Afterglow of a Pulsed Inductively Coupled RF
Plasma. Plasma Sources Science Technology 16, 355-363
(2007).
Pacher, H. D., A. S. Kukushkin, G. W. Pacher, G. Janeschitz,
D. Coster, V. Kotov and D. Reiter: Effect of the tokamak size
in edge transport modelling and implications for DEMO.
Journal of Nuclear Materials 363-365, 400-406 (2007).
Padberg, K., T. Hauff, F. Jenko and O. Junge: Lagrangian
structures and transport in turbulent magnetized plasmas.
New Journal of Physics 9, 400 (2007).
http://www.iop.org/EJ/abstract/1367-2630/9/11/400
Pan, Y. D. and R. Schneider: Study of the specific detachment
characteristics of HL-2A. Journal of Nuclear Materials
363-365, 407-411 (2007).
Peeters, A. G., C. Angioni, A. C. C. Sips and ASDEX Upgrade
Team: On the extrapolation to ITER of discharges in present
tokamaks. Nuclear Fusion 47, 1341-1345 (2007).
Peeters, A. G., C. Angioni and D. Strintzi: Toroidal Momentum
Pinch Velocity due to the Coriolis Drift Effect on Small
Scale Instabiltities in a Toroidal Plasma. Physical Review
Letters 98, 265003 (2007).
Pautasso, G., C. J. Fuchs, O. Gruber, C.F. Maggi, M. Maraschek,
T. Pütterich, V. Rohde, C. Wittmann, E. Wolfrum, P. Cierpka,
M. Beck and ASDEX Upgrade Team: Plasma shut-down with
fast impurity puff on ASDEX Upgrade. Nuclear Fusion 47,
900-913 (2007).
Perfilov, S., A. Melnikov, L. Krupnik and H.-J. Hartfuß:
Applicability of heavy-ion-beam probing for stellarator W7-X.
Fusion Science and Technology 51, 38-45 (2007).
Publications
132
Piazza, G., G. F. Matthews, J. Pamela, H. Altmann, J. P. Coad,
T. Hirai, A. Lioure, H. Maier, Ph. Mertens, V. Philipps,
V. Riccardo, M. Rubel, E. Villedieu and Collaborators of the
JET ITER-like Project: R&D on tungsten plasma facing
components for the JET ITER-like wall project. Journal of
Nuclear Materials 367-370, 1438-1443 (2007).
Pitts, R. A., P. Andrew, G. Arnoux, T. Eich, W. Fundamenski,
A. Huber, C. Silva, D. Tskhakaya and JET EFDA Contributors:
ELM Transport in the JET Scrape-off Layer. Nuclear Fusion 47,
1437-1448 (2007).
Pitts, R. A., J. Horacek, W. Fundamenski, O. E. Garcia,
A. H. Nielsen, M. Wischmeier, V. Naulin and J. Juul Rasmussen:
Parallel SOL flow on TCV. Journal of Nuclear Materials
363-365, 505-510 (2007).
Plankensteiner, A., A. Leuprecht, B. Schedler, K. H. Scheiber
and H. Greuner: Finite element based design optimization
of Wendelstein 7-X divertor components under high heat
flux loading. Fusion Engineering and Design 82, 1813-1819
(2007).
Pochelon, A., A. Mueck, L. Curchod, Y. Camenen, S. Coda,
B. P. Duval, T. P. Goodman, I. Klimanov, H. P. Laqua,
Y. Martin, J.-M. Moret, L. Porte, A. Sushkov, V. S. Udintsev,
F. Volpe and TCV Team: Electron Bernstein wave heating of
over-dense H-mode plasmas in the TCV tokamak via O-X-B
double mode conversion. Nuclear Fusion 47, 1552-1558 (2007).
Podoba, Y. Y., H. P. Laqua, G. B. Warr, M. Schubert, M. Otte,
S. Marsen, F. Wagner and E. Holzhauer: Direct Observation
of Electron Bernstein Wave Heating by OXB Mode conversion
at low magnetic field in the WEGA Stellarator. Physical
Review Letters 98, 255003 (2007).
Pokol, G., G. Por, S. Zoletnik and W7-AS Team: Application of
a bandpower correlation method to the statistical analysis of
MHD bursts in quiescent Wendelstein-7 AS stellarator plasmas.
Plasma Physics and Controlled Fusion 49, 1391-1408 (2007).
Poulipoulis, G., G. N. Throumoulopoulos and H. Tasso: Twofluid
tokamak equilibria with reversed magnetic shear and
sheared flow. Journal of Plasma Physics 73, 347-366 (2007).
Primetzhofer, D., S. N. Markin, R. Kolarova, M. Draxler,
R. Beikler, E. Taglauer and P. Bauer: On the Surface Sensitivity
of Angular Scans in LEIS. Nuclear Instruments and
Methods in Physics Research B: Beam Interactions with
Materials and Atoms 258, 36-39 (2007).
Pugno, R., M. J. Baldwin, R. P. Doerner, J. Hanna, D. Nishijima
and G. Antar: Surface effects on graphite samples exposed

to beryllium-seeded plasmas under transient power load on
PISCES-B. Journal of Nuclear Materials 363-365, 1277-1282
(2007).
Radtke, R., C. Biedermann, P. Mandelbaum and J. L. Schwob:
X ray and EUV spectroscopic measurements of highly charged
tungsten ions relevant to fusion plasmas. Journal of Physics.
Conference Series 58, 113-116 (2007).
Rai, A., P. N. Maya, R. Schneider, S. P. Deshpande and M. Warrier:
Dynamic Monte-Carlo modeling of hydrogen isotope diffusion
in co-deposited layers. Journal of Nuclear Materials 363-365,
1272-1276 (2007).
Ramponi, G., D. Farina, M. A. Henderson, E. Poli, G. Saibene
and H. Zohm: ITER ECRH-ECCD System Capabilities for
Extended Physics Applications. Fusion Science and Technology
52, 193-201 (2007).
Raupp, G., W. Treutterer, V. Mertens, G. Neu, A. Sips, D. Zasche,
T. Zehetbauer and ASDEX Upgrade Team: Control processes
and machine protection on ASDEX Upgrade. Fusion Engineering
and Design 82, 1102-1110 (2007).
Reich, J., A. Cardella, A. Capriccioli, T. Koppe, B. Missal,
W. Löhrer, S. Langone and P.-C. Sassone: Experimental verification
of the axial and lateral stiffness of large W7-X rectangular
bellows. Fusion Engineering and Design 82, 1924-1928 (2007).
Reiman, A. A., M. C. Zarnstorff, D. Monticello, A. Weller,
J. Geiger and W7-AS Team: Pressure-induced, breaking of
equilibrium flux surfaces in the W7AS stellarator. Nuclear
Fusion 47, 572-578 (2007).
Reinelt, M. and C. Linsmeier: Enhanced room temperature
erosion of ultra-thin carbon films on beryllium, titanium and
tantalum by deuterium ions. Nuclear Instruments and Methods
in Physics Research B: Beam Interactions with Materials
and Atoms 258, 270-273 (2007).
Reinelt, M. and C. Linsmeier: Temperature programmed
desorption of 1 keV deuterium implanted into clean beryllium.
Physica Scripta T128, 111-114 (2007).
Rohde, V., R. Dux, A. Kallenbach, K. Krieger, R. Neu and
ASDEX Upgrade Team: Wall conditioning in ASDEX Upgrade.
Journal of Nuclear Materials 363-365, 1369-1374 (2007).
Roth, J., V. K. Alimov, A. Golubeva, R. Doerner, J. Hanna,
E. Tsitrone, C. Brosset, V. Rohde, A. Herrmann and M. Mayer:
Deuterium retention in carbon fibre composites NB31 and
N11 irradiated with low-energy D ions. Journal of Nuclear
Materials 363-365, 822-826 (2007).
Publications
133
Roth, J., E. Tsitrone and A. Loarte: Plasma-Wall-Interaction:
Important Ion Induced Surface Processes and Strategy of the
EU Task Force. Nuclear Instruments and Methods in Physics
Research B: Beam Interactions with Materials and Atoms 258,
253-363 (2007).
Rozhansky, V., P. Molchanov, S. Voskoboynikov, G. Counsell,
D. Coster and R. Schneider: Modeling of the parametric
dependence of the edge toroidal rotation for MAST and
ASDEX Upgrade. Journal of Nuclear Materials 363-365,
664-668 (2007).
Rudakov, D. L., W. Jacob, K. Krieger, A. Litnovsky, V. Philipps,
W. P. West, C. P. C. Wong, S. L. Allen, R. J. Bastasz, J. A. Boedo,
N. H. Brooks, R. L. Boivin, G. De Temmerman, M. E. Fenstermacher,
M. Groth, E. M. Hollmann, C. J. Lasnier, A. G. McLean,
R. A. Moyer, P. C. Stangeby, W. R. Wampler, J. G. Watkins,
P. Wienhold and J. Whaley: DiMES studies of temperature
dependence of carbon erosion and re-deposition in DIII-D
divertor. Physica Scripta T128, 29-34 (2007).
Rummel, K., M. Czerwinski, F. Hurd, A. John, H. Lentz, G. Czymek,
B. Giesen, F. Harberts, S. A. Egorov, V. E. Korsunsky, I. Y. Rodin,
P. Bruzzone, B. Stepanov and M. Vogel: Test results from the
full size prototype test of W7-X joint. Fusion Engineering
and Design 82, 1526-1531 (2007).
Ruset, C., E. Grigore, H. Maier, R. Neu, X. Li, H. Dong,
R. Mitteau and X. Courtois: W coatings deposited on CFC
tiles by Combined Magnetron Sputtering and Ion Implantation
technique. Physica Scripta T128, 171-174 (2007).
Sadykova, S. and W. Ebeling: Electric Microfield Distributions
in Dense One- and Two-Component Plasmas. Contributions
to Plasma Physics 47, 659-669 (2007).
Saibene, G., N. Oyama, J. Lönroth, Y. Andrew, E. de la Luna,
C. Giroud, G. T. A. Huysmans, Y. Kamada, M. A .H. Kempenaars,
A. Loarte, D. McDonald, M. M. F Nave, A. Meiggs, V. Parail,
R. Sartori, S. Sharapov, J. Stober, T. Suzuki, M. Takechi, K. Toi
and H. Urano: The H-mode pedestal, ELMs and TF ripple
effects in JT-60U/JET dimensionless identitity experiments.
Nuclear Fusion 47, 969-983 (2007).
Salancon, E., T. Dürbeck, T. Schwarz-Selinger and W. Jacob:
Reactivity of soft amorphous hydrogenated carbon films in
ambient atmosphere. Journal of Nuclear Materials 363-365,
944-948 (2007).
Sardei, F., Y. Feng, J. Kißlinger, P. Grigull, M. Kobayashi,
D. Harting, D. Reiter, G. Federici and A. Loarte: Non-axisymmetric
SOL-transport study for tokamaks and stellarators.
Journal of Nuclear Materials 363-365, 511-516 (2007).

Sborchia, C.: The Manufacture of the W7-X Superconducting
Magnet System as Relevant Experience for the Construction
of the Next Fusion Devices. IEEE Transactions on Applied
Superconductivity 17, 1334-1337 (2007).
Scarabosio, A., A. Pochelon and Y. Martin: Plasma shape
stabilization of current rise MHD instabilities in TCV. Plasma
Physics and Controlled Fusion 49, 1019-1039 (2007).
Schacht, J., H. Laqua, M. Lewerentz, I. Müller, S. Pingel,
A. Spring and A. Wölk: Overview and status of the control
system of Wendelstein 7-X. Fusion Engineering and Design 82,
988-994 (2007).
Schauer, F. and W7-X Team: Status of Wendelstein 7-X Construction.
Fusion Engineering and Design 82, 443-453 (2007).
Schirmer, J., G. D. Conway, E. Holzhauer, W. Suttrop, H. Zohm
and ASDEX Upgrade Team: Radial correlation length measurements
on ASDEX Upgrade using correlation Doppler
reflectometry. Plasma Physics and Controlled Fusion 49,
1019-1039 (2007).
Schlosser, J., E. Martin, C. Henninger, J. Boscary, G. Camus,
F. Escourbiac, D. Leguillon, M. Missirlian and R. Mitteau:
CFC/Cu bond damage in actively cooled plasma facing
components. Physica Scripta T128, 204-208 (2007).
Schmid, K., M. J. Baldwin, R. P. Doerner and D. Nishijima:
Beryllium layer deposition on carbon and tungsten from beryllium-seeded
plasmas. Nuclear Technology 159, 238-244 (2007).
Schmid, A., A. Herrmann, V. Rohde, M. Maraschek, H. W. Müller
and ASDEX Upgrade Team: Magnetically driven filament
probe. Review of Scientific Instruments 78, 053502 (2007).
Schmid, M., S. Illya, G. Dammertz, V. Erckmann and M. Thumm:
Transverse field collector sweep system for high power CW
gyrotrons. Fusion Engineering and Design 82, 744-750 (2007).
Schmid, K., K. Krieger, A. Kukushkin and A. Loarte:
DIVIMP modelling of tungsten impurity transport in ITER.
Journal of Nuclear Materials 363-365, 674-679 (2007).
Schmid, K., T. Schwarz-Selinger, W. Jacob, R. Dux and
ASDEX-Upgrade Team: The implications of high-Z first
wall materials on noble gas wall recycling. Nuclear Fusion 47,
984-989 (2007).
Schneider, R., A. Rai, A. Mutzke, M. Warrier, E. Salonen and
K. Nordlund: Dynamic Monte-Carlo modeling of hydrogen
isotope reactive-diffusive transport in porous graphite.
Journal of Nuclear Materials 367-370, 1238-1242 (2007).
Publications
134
Schneider, R. and A. Runov: Challenges in plasma edge fluid
modelling. Plasma Physics and Controlled Fusion 49, S87-S95
(2007).
Schröder, M., J. Holluba and K. Heyn: Quality assurance of
aluminium weld seams and cast casings of the W7-X coils.
Fusion Engineering and Design 82, 1532-1537 (2007).
Schubert, T., A. Brendel, K. Schmid, T. Koeck, L. Ciupinski,
W. Zielinski, T. Weißgärber and B. Kieback: Interfacial design
of Cu/SiC composites prepared by Powder Metallurgy for
Heat sink applications. Composites Part A: Applied Science
and Manufacturing 38, 2398-2403 (2007).
Schubert, M., M. Endler, H. Thomsen and W7-AS Team:
Spatio-temporal temperature fluctuation measurements by
means of a fast swept Langmuir probe array. Review of
Scientific Instruments 78, 053505 (2007).
Schustereder, W., A. Herrmann, V. Rohde and ASDEX Upgrade
Team: Impurity survey after Boronization in ASDEX Upgrade
measured by a collector probe. Physica Scripta T128, 14-17
(2007).
Schustereder, W., K. Krieger, A. Herrmann, V. Rohde and
ASDEX Upgrade Team: Discharge resolved impurity flux
measurements in the edge plasma of ASDEX Upgrade by
exposure of collector probes. Journal of Nuclear Materials
363-365, 242-246 (2007).
Schustereder, W., B. Rasul, N. Endstrasser, V. Grill, P. Scheier
and T. Märk: Sticking Coefficient and SIMS of Hydrocarbons
on Fusion Relevant Plasma-Sprayed Tungsten Surfaces.
Nuclear Instruments and Methods in Physics Research B:
Beam Interactions with Materials and Atoms 258, 278-281
(2007).
Schwarz-Selinger, T., C. Hopf, C. Sun and W. Jacob: Growth
and erosion of amorphous carbon (a-C:H) films by low-temperature
laboratory plasmas containing H and N mixtures.
Journal of Nuclear Materials 363-365, 174-178 (2007).
Scott, B. D.: Nonlinear polarization and dissipative correspondence
between low-frequency fluid and gyrofluid equations.
Physics of Plasmas 14, 102318 (2007).
Scott, B. D.: Tokamak edge turbulence: background theory
and computation. Plasma Physics and Controlled Fusion 49,
S25-S41 (2007).
Scott, S., A. Bader, M. Bakhtiari, N. Basse, W. Beck, T. Biewer,
S. Bernabei, P. Bonoli, B. Bose, R. Bravenec, I. Bespamyatnov,
R. Childs, I. Cziegler, R. Doerner, E. Edlund, D. Ernst, A. Fasoli,

M. Ferrara, C. Fiore, T. Fredian, A. Graf, T. Graves, R. Granetz,
N. Greenough, M. Greenwald, M. Grimes, O. Grulke, D. Gwinn,
R. Harvey, S. Harrison, T. C. Hender, J. Hosea, D. F. Howell,
A. E. Hubbard, J. W. Hughes, I. Hutchinson, A. Ince-Cushman,
J. Irby, T. Jernigan, D. Johnson, J. Ko, P. Koert, B. LaBombard,
A. Kanojia, L. Lin, Y. Lin, B. Lipschultz, J. Liptac, A. Lynn,
P. MacGibbon, E. Marmar, K. Marr, M. May, D. R. Mikkelsen,
R. McDermott, A. Parisot, R. Parker, C. K. Phillips, P. Phillips,
M. Porkolab, M. Reinke, J. Rice, W. Rowan, M. Sampsell,
G. Schilling, A. Schmidt, N. Smick, A. Smirnov, J. Snipes, D. Stotler,
J. Stillerman, V. Tang, D. Terry, J. Terry, M. Ulrickson, R. Vieira,
G. Wallace, D. Whyte, J. R. Wilson, G. Wright, J. Wright, S. Wolfe,
S. Wukitch, G. Wurden, H. Yuh, K. Zhurovich, J. Zaks and
S. Zweben: Overview of the Alcator C-MOD research programme.
Nuclear Fusion 47, S598-S607 (2007).
Sengupta, A., J. Geiger and P. J. Mc Carthy: Statistical
Analysis of the equilibrium configurations of W7-X stellarator.
Plasma Physics and Controlled Fusion 49, 649-673 (2007).
Sharma, A., R. Schneider, U. von Toussaint and K. Nordlund:
Hydrocarbon radicals interaction with amorphous carbon surfaces.
Journal of Nuclear Materials 363-365, 1283-1288 (2007).
Shimada, M., D. J. Campbell, V. Mukhovatov, M. Fujiwara,
N. Kirneva, K. Lackner, M. Nagami, V. D. Pustovitov, N. Uckan,
J. Wesley, N. Asakura, A. E. Costley, A. J. H. Donne, E. J. Doyle,
A. Fasoli, C. Gormezano, Y. Gribov, O. Gruber, T. C. Hender,
W. Houlberg, S. Ide, Y. Kamada, A. Leonard, B. Lipschultz,
A. Loarte, K. Miyamoto, V. Mukhovatov, T. H. Osborne, A. Polevoi
and A. C. C. Sips: Chapter 1: Overview and summary. Nuclear
Fusion 47, S1-S17 (2007).
Shimizu, S., T. Shimizu, B. M. Annaratone, W. Jacob, C. Linsmeier,
S. Lindig, R. W. Stark, F. Jamitzky, H. Thomas, N. Sato and
G. E. Morfill: The approach to diamond growth on the levitated
seed particles. Applied Surface Science 254, 177-180 (2007).
Sips, A. C. C., G. Tardini, C. B. Forest, O. Gruber, P. J. McCarthy,
A. Gude, L. D. Horton, V. Igochine, O. Kardaun, C. F. Maggi,
M. Maraschek, V. Mertens, R. Neu, A. G. Peeters, G. V. Pereverzev,
A. Stäbler, J. Stober, W. Suttrop and ASDEX Upgrade Team:
The performance of improved H-modes at ASDEX Upgrade
and projection to ITER. Nuclear Fusion 47, 1485-1498 (2007).
Soddemann, T.: Science Gateways to DEISA: User requirements,
technologies, and the material science and plasma
physics gateway. Concurrency and Computing: Practice and
Experience 19, 839-850 (2007).
Spring, A., H. Laqua and J. Schacht: User control interface
for W7-X plasma operation. Fusion Engineering and Design 82,
1002-1007 (2007).
Publications
135
Stan-Sion, C., J. Roth, K. Krieger, M. Enachescu, K. Ertl,
V. Lazarev, H. Reithmeier and E. Nolte: AMS – Sensitive
tool used as nuclear safeguard and to diagnose fusion experiments.
Nuclear Instruments and Methods in Physics
Research B: Beam Interaction with Materials and Atoms 259,
694-701 (2007).
Starke, P., C. Adelhelm and M. Balden: Erosion Behaviour
of Metal-Doped Carbon Layers in Deuterium Low Pressure
Plasmas and the Determination by Optical Emission Spectroscopy.
Contributions to Plasma Physics 47, 530-536 (2007).
Stober, J., A. C. C. Sips, C. Angioni, C. B. Forest, O. Gruber,
J. Hobirk, L. D. Horton, C. F. Maggi, M. Maraschek, P. Martin,
P. J. McCarthy, V. Mertens, Y.-S. Na, M. Reich, A. Stäbler,
G. Tardini, H. Zohm and ASDEX Upgrade Team: The role of
the current profile in the improved H-mode scenario in
ASDEX Upgrade. Nuclear Fusion 47, 728-737 (2007).
Strintzi, D. and F. Jenko: On the relation between secondary
and modulational instabilities. Physics of Plasmas 14, 042305
(2007).
Sugiyama, K., T. Hayshi, K. Krieger, M. Mayer, K. Masaki,
N. Miya and T. Tanabe: Ion Beam analysis of H/D retention
in the near surface layers of JT-60U plasma facing wall tiles.
Journal of Nuclear Materials 363-365, 949-954 (2007).
Taccogna, F., S. Longo, M. Capitelli and R. Schneider:
Particle-in-Cell Simulation of Stationary Plasma Thruster.
Contributions to Plasma Physics 47, 635-656 (2007).
Taccogna, F., R. Schneider, U. Fantz, S. Longo and M. Capitelli:
Study of volume and surface effects in pure hydrogen discharges.
Production and Neutralization of Negative Ions and
Beams. (Ed.) M. P. Stockli. AIP Conference Proceedings 925.
American Institute of Physics, Melville, NY (2007) 20-30.
Taccogna, F., R. Schneider, S. Longo and M. Capitelli:
Modeling of a negative ion source I. Gas kinetics and dynamics
in the expansion region. Physics of Plasmas 14, 073503 (2007).
Taccogna, F., R. Schneider, K. Matyash, S. Longo, M. Capitelli
and D. Tskhakaya: Negative ion production near a divertor
plate. Journal of Nuclear Materials 363-365, 437-442 (2007).
Takeiri, Y., O. Kaneko, K. Tsumori, U. Fantz, K. Ikeda, K. Nagaoka,
M. Osakabe, Y. Oka, E. Asano, T. Kondo, M. Sato, M. Shibuya
and S. Komada: High-power negative ion sources for neutral
beam injectors in large helical device. Production and Neutralization
of Negative Ions and Beams. (Ed.) M. P. Stockli. AIP
Conference Proceedings 925. American Institute of Physics,
Melville, NY (2007) 211-223.

Tala, T., K. Crombe, P. C. De Vries, J. Ferreira, P. Mantica,
A. G. Peeters, Y. Andrew, R. Budny, G. Corrigan, A. Eriksson,
X. Garbet, C. Giroud, M.-D. Hua, H. Nordman, V. Naulin,
M. F. F. Nave, V. Parail, K. Rantamäki, B. D. Scott, P. Strand,
G. Tardini, A. Thyagaraja, J. Weiland, K.-D. Zastrow and
JET-EFDA Contributors: Toroidal and poloidal momentum
transport studies in tokamaks. Invited Paper. Plasma Physics
and Controlled Fusion 49, B291-B302 (2007).
Tambach, S. and C. Hennig: Wie zuverlässig ist der Empfang
von Netzwerkpaketen bei der Verwendung des Transportprotokolls
UDP? Informatik-Spektrum 30, 84-90 (2007).
Tardini, G., J. Hobirk, V. Igochine, C. V. Maggi, P. Martin,
D. McCune, A. G. Peeters, A. C. C. Sips, A. Stäbler, J. Stober
and ASDEX Upgrade Team: Thermal ions dilution and ITG
suppression in ASDEX Upgrade ion ITBs. Nuclear Fusion 47,
280-287 (2007).
Tasso, H. and G. N. Throumoulopoulos: On the existence of
resistive magnetohydrodynamic equilibria. (Letter to the
Editor). Journal of Plasma Physics 73, 285-287 (2007).
Tasso, H. and G. N. Throumoulopoulos: On the Vlasov approach
to tokamak equilibria with flow. Journal of Physics A:
Mathematical and Theoretical 40, F631-F637 (2007).
Thehos, K.: IPP 2006 – Das Max-Planck-Institut für Plasmaphysik
im Jahresrückblick. Max-Planck-Institut für Plasmaphysik.
Pressestelle, Garching bei München (2007), 31 p.
Throumoulopoulos, G. N., H. Weitzner and H. Tasso: On
nonexistence of tokamak equilibria with purely poloidal
flow. Physics of Plasmas 13, 122501 (2007).
Thumm, M., S. Alberti, A. Arnold, P. Brand, H. Braune, G. Dammertz,
V. Erckmann, G. Gantenbein, E. Giguet, R. Heidinger, J. P. Hogge,
S. Illy, W. Kasparek, H. P. Laqua, F. Legrand, W. Leonhardt,
C. Lievin, G. Michel, G. Neffe, B. Piosczyk, M. Schmid, K. Schwörer
and M. Q. Tran: EU megawatt-class 140 GHz CW gyrotron.
IEEE Transactions on Plasma Science 35, 143-153 (2007).
Tsalas, M., D. Coster, C. Fuchs, A. Herrmann, A. Kallenbach,
H. W. Müller, J. Neuhauser, V. Rohde, N. Tsois and ASDEX
Upgrade Team: In-out divertor flow asymmetries during
ELMs in ASDEX Upgrade H-mode plasmas. Journal of
Nuclear Materials 363-365, 1093-1098 (2007).
Tsalas, M., A. Herrmann, A. Kallenbach, H. W. Müller,
J. Neuhauser, V. Rohde, N. Tsois, M. Wischmeier and ASDEX
Upgrade Team: Divertor plasma flows near the lower x-point in
ASDEX Upgrade. Plasma Physics and Controlled Fusion 49,
857-872 (2007).
Publications
136
Tskhakaya, D., K. Matyash, R. Schneider and F. Taccogna:
The Particle-In-Cell Method. Contributions to Plasma
Physics 47, 563-594 (2007).
Tskhakaya, D. and R. Schneider: Optimization of PIC codes
by improved memory management. Journal of Computational
Physics 225, 829-839 (2007).
Turkin, Y., C. D. Beidler, A. Dinklage, J. Geiger, H. Maaßberg,
N. B. Marushchenko and W7-X Team: Transport simulations
for W7-X. Stellarator News, 4-8 (2007).
http://www.ornl.gov/sci/fed/stelnews/sn107.pdf
Tykhyy, A. V., Y. I. Kolesnichenko, Y. V. Yakovenko, A. Weller and
A. Werner: Mitigation of stochastic diffusion losses in optimized
stellarators. Plasma Physics and Controlled Fusion 49,
703-711 (2007).
Vainonen-Ahlgren, E., J. Likonen, T. Renvall, V. Rohde,
M. Mayer and ASDEX Upgrade Team: Migration of 13 C and
deposition at ASDEX Upgrade. Journal of Nuclear Materials
363-365, 270-275 (2007).
Veres, G., R. A. Pitts, M. Wischmeier, B. Gulejova, J. Horacek
and S. Kalvin: Radiation distributions in TCV. Journal of
Nuclear Materials 363-365, 1104-1109 (2007).
Verhoeven, A. G. A., W. A. Bongers, A. Bruschi, S. Cirant,
I. Danilov, B. S. Q. Elzendoorn, A. Fernandez, M. F. Graswinckel,
R. Heidinger, M. Henderson, J. Jamar, W. Kasparek, O. G. Kruijt,
B. Lamers, B. Plaum, D. M. S. Ronden, G. Saibene, F. C. Schüller,
E. Westerhof and H. Zohm: Design of the remote-steering
ITER ECRH upper-port launcher. Fusion Engineering and
Design 82, 627-632 (2007).
Vermare, L., F. Ryter, C. Angioni, A. G. Peeters, J. Stober,
R. Bilato, L. D. Horton, B. Kurzan, C. F. Maggi, H. Meister,
J. Schirmer, G. Tardini and ASDEX Upgrade Team: Study of
the β dependence of confinement and heat transport in
ASDEX Upgrade. Nuclear Fusion 47, 490-497 (2007).
Von Toussaint, U. and S. Gori: Deconvolution using thinplate
splines. Bayesian Inference and Maximum Entropy
Methods in Science and Engineering: 27 th International
Workshop on Bayesian Inference and Maximum Entropy
Methods in Science and Engineering. (Eds.) K. H. Knuth,
A. Caticha, J. L. Center, A. Giffin, C. C. Rodriguez. AIP
Conference Proceedings 954. American Institute of Physics,
Melville, NY, 212-220 (2007).
Vrancken, M., M.-L. Mayoral, T. Blackman, V. V. Bobkov,
D. Child, P. Dumortier, F. Durodie, M. Evrard, R. H. Goulding,
M. Graham, S. Huygen, P. U. Lamalle, F. Louche, A. M. Messiaen,

I. Monakhov, M. P. S. Nightingale, J.-M. Noterdaeme,
J. Ongena, D. Stork, M. Vervier, A. Walden, A. Whitehurst and
JET-EFDA Contributors: Recent ICRF developments at JET.
Fusion Engineering and Design 82, 873-880 (2007).
Wagner, D., F. Leuterer, A. Manini, F. Monaco, M. Münich,
F. Ryter, H. Schütz, J. Stober, H. Zohm, T. Franke, I. Danilov,
R. Heidinger, M. Thumm, G. Gantenbein, W. Kasparek, C. Lechte,
A. Litvak, G. Denisov, E. Tai, L. Popov, V. Nichiporenko,
V. Myasnikov, E. Solyanova, S. Malygin, F. Meo and P. Woskov:
The New Multifrequency Electron Cyclotron Resonance
Heating System for ASDEX Upgrade. Fusion Science and
Technology 52, 313-320 (2007).
Wagner, F.: About the European Physical Society (EPS).
Butsuri 62, 536-540 (2007).
Wagner, F.: On the impact of experts. Europhysics News 38, 4,
5-6 (2007).
Wagner, F.: A quarter-century of H-mode studies. Invited Paper.
Plasma Physics and Controlled Fusion 49, B1-B33 (2007).
Wagner, F.: Is truth still of value? Europhysics News 38, 5,
5-6 (2007).
Wagner, F.: My views and programme. Europhysics News 38, 3,
5-9 (2007).
Waldmann, O., H. Meyer and G. Fußmann: Anomalous
Diffusion in a Linear Plasma Generator. Contributions to
Plasma Physics 47, 691-702 (2007).
Wanner, M., C. Sborchia, K. Riße, H. Viebke and J. Baldzuhn:
Experience gained during manufacture and testing of the
W7-X superconducting magnets. Fusion Engineering and
Design 82, 1379-1384 (2007).
Warrier, M., R. Schneider, E. Salonen and K. Nordlund:
Effect of the porous structure of graphite on atomic hydrogen
diffusion and inventory. Nuclear Fusion 47, 1656-1663 (2007).
Wegener, L.: Wendelstein 7-X at the transition to assembly.
Atomwirtschaft 52, 8/9, 558-563 (2007).
Wenzel, U., D. Schröder and G. Fußmann: Appearance of a H α
Minimum at the Onset of Net Recombination in Hydrogen
Plasmas. Contributions to Plasma Physics 47, 451-457 (2007).
Wenzel, U., H. Thomsen and P. Grigull: Carbon influx from
the island divertor of the Wendelstein-7AS stellarator.
Journal of Nuclear Materials 363-365, 713-717 (2007).
Publications
137
Wiltner, A., F. Kost, S. Lindig and C. Linsmeier: Structural
investigation of the Be-W intermetallic system. Physica
Scripta T128, 133-136 (2007).
Windisch, T., O. Grulke and T. Klinger: Radially propagating
turbulent structures in a linear helicon plasma device.
Journal of Nuclear Materials 363-365, 586-590 (2007).
Winter, B., E. F. Aziz, U. Hergenhahn, M. Faubel and I. V. Hertel:
Hydrogen bonds in liquid water studied by photoelectron
spectroscopy. Journal of Chemical Physics 126, 124504
(2007).
Winter, B., U. Hergenhahn, M. Faubel, O. Björneholm and
I. V. Hertel: Hydrogen bonding in liquid water probed by
resonant Auger-electron spectroscopy. Journal of Chemical
Physics 127, 094501 (2007).
Wischmeier, M., A. Kallenbach, A. V. Chankin, D. P. Coster,
T. Eich, A. Herrmann, H. W. Müller and ASDEX Upgrade
Team: High recycling outer divertor regimes after type-I
ELMs at high density in ASDEX Upgrade. Journal of Nuclear
Materials 363-365, 448-452 (2007).
Wong, C., D. Rudakov, J. Allain, R. Bastasz, N. Brooks,
J. Brooks, R. Doerner, T. Evans, A. Hassanein, W. Jacob,
K. Krieger, A. Litnovsky, A. McLean, V. Philipps, A. Pigarov,
W. Wampler, J. Watkins, W. West, J. Whaley and P. Wienhold:
Divertor and Midplane Materials Evaluation System in
DIII-D. Journal of Nuclear Materials 363-365, 276-281
(2007).
Wünderlich, D., R. Gutser and U. Fantz: Influence of Magnetic
Fields and Biasing on the Plasma of a RF Driven
Negative Ion Source. Production and Neutralization of Negative
Ions and Beams. (Ed.) M. P. Stockli. AIP Conference
Proceedings 925. American Institute of Physics, Melville, NY,
46-57 (2007).
Xanthopoulos, P. and F. Jenko: Gyrokinetic analysis of linear
microinstabilities for the stellarator Wendelstein 7-X. Physics
of Plasmas 14, 042501 (2007).
Xanthopoulos, P., F. Merz, T. Görler and F. Jenko: Nonlinear
gyrokinetic simulations of ion-temperature-gradient
turbulence for the optimized stellarator Wendelstein 7-X.
Physical Review Letters 99, 035002 (2007).
Yakovenko, Y., A. Weller, A. Werner, S. Zegenhagen, O. P. Fesenyuk
and Y. Kolesnichenko: Poloidal trapping of the high-frequency
Alfvén continuum and eigenmodes in stellarators.
Plasma Physics and Controlled Fusion 49, 535-558 (2007).

Yamamoto, S., K. Nagasaki, Y. Suzuki, T. Mizuuchi, H. Okada,
S. Kobayashi, B. Blackwell, K. Kondo, G. Motojima, N. Nakajima,
Y. Nakamura, C. Nührenberg, Y. Torii, S. Watanabe and F. Sano:
Observation of Magnetohydrodynamic Instabilities in
Heliotron J Plasmas. Fusion Science and Technology 51,
92-96 (2007).
Yao, Z., A. Suzuki, D. Levchuk and T. Terai: SiC coating by
RF sputtering as tritium permeation barrier for fusion blanket.
Fusion Science and Technology 52, 865-869 (2007).
Yokoyama, M., H. Maaßberg, C. D. Beidler, V. Tribaldos, K. Ida,
T. Estrada, F. Castejon, A. Fujisawa, T. Minami, T. Shimozuma,
Y. Takeiri, A. Dinklage, S. Murakami and H. Yamada: Core
electron-root confinement (CERC) in helical plasmas. Nuclear
Fusion 47, 1213-1219 (2007).
Yu, Q.: Heat diffusion across a local stochastic magnetic
field. Nuclear Fusion 47, 1244-1249 (2007).
Zohm, H.: 21 st IAEA Fusion Energy Conference: Summary
of Sessions EX/D, EX/S and EX/W. Nuclear Fusion 47,
S521-S528 (2007).
Zohm, H.: Recent Experimental Progress in Electron Cyclotron
Resonance Heating and Electron Cyclotron Current Drive in
Magnetically Confined Fusion Plasmas. Fusion Science and
Technology 52, 134-144 (2007).
Zohm, H., G. Gantenbein, F. Leuterer, A. Manini, M. Maraschek,
Q. Yu and ASDEX Upgrade Team: Control of MHD Instabilities
by ECCD: ASDEX Upgrade Results and Impliations
for ITER. Nuclear Fusion 47, 228-232 (2007).
Zohm, H., G. Gantenbein, F. Leuterer, M. Maraschek, E. Poli,
L. Urso and ASDEX Upgrade Team: Control of NTMs by
ECCD on ASDEX Upgrade in view of ITER application.
Invited Paper. Plasma Physics and Controlled Fusion 49,
B341-B348 (2007).
Zweben, S. J., J. A. Boedo, O. Grulke, C. Hidalgo, B. LaBombard,
R. J. Maqueda, P. Scarin and J. L. Terry: Edge turbulence
measurements in toroidal fusion devices. Plasma Physics
and Controlled Fusion 49, S1-S23 (2007).
Publications
138
Conference Papers
Angioni, C., A. Manini, A. G. Peeters, F. Ryter, R. Dux, A. Jacchia,
C. F. Maggi, R. Neu, W. Suttrop, G. Tardini and ASDEX
Upgrade Team: Theoretical understanding of core transport
phenomena in ASDEX Upgrade. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, EX/8-5Rb (2007).
Antar, G. Y., M. Tsalas, E. Wolfrum, V. Rohde, B. Scott and
J. Neuhauser: Comparing Turbulence in L and H-mode plasmas
in the Scrape-off Layer of the ASDEX-Upgrade Tokamak.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.076
(2007).
Atanasiu, C. V., S. Günter, A. Moraru and L.E. Zakharov:
Resistive Wall Modes Stabilization in the Presence of 3D Wall
Structures. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-4.086
(2007).
Bertelli, N., G. V. Pereverzev and E. Poli: Beam Tracing
description of LH waves in tokamaks. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-5.051 (2007).
Bonnin, X., D. P. Coster, M. Warrier and R. Schneider: Integrated
modelling of plasma-wall interactions in tokamaks
with B2.5: mixed materials, layers and coatings, bundled
charge states, and hydrogen inventory. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-4.036 (2007).
Bovshuk, V. R., W. A. Cooper, M. I. Mikhailov, J. Nührenberg
and V. D. Shafranov: Search for quasi-isodynamic configurations
with diminished parallel current density. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F. European
Physical Society, Geneva, P-4.103 (2007).
Braune, H., P. Brand, G. Dammertz, V. Erckmann, G. Gantenbein,
W. Kasparek, H. P. Laqua, W. Leonhardt, D. Mellein, G. Michel,
F. Noke, F. Purps, K.-H. Schlüter, M. Schmid, M. Thumm
and W7-X ECRH Teams at IPP, IPF and FZK: Extended
operation of the 1 MW, CW gyrotrons for W7-X. IRMMW-THz
2007: Conference Digest of the 32 nd International Conference
on Infrared and Millimeter Waves, and 15 th International
Conference on Terahertz Electronics, IEEE Operation Center,
Piscataway, NJ, CD-ROM, 104-105 (2007).

Camplani, M., B. Cannas, A. Fanni, G. Pautasso, S. Sias,
P. Sonato, M. K. Zedda and ASDEX Upgrade Team: Mapping of
the ASDEX Upgrade Operational Space using Clustering Techniques.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-5.144 (2007).
Chankin, A. V., D. P. Coster, G. Corrigan, S. K. Erents,
W. Fundamenski, A. Kallenbach, K. Lackner, J. Neuhauser,
R. Pitts, ASDEX Upgrade Team and JET-EFDA Contributors:
Mechanisms Affecting Radial Electric Field in the Tokamak
SOL. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-4.029 (2007).
Chankin, A. V., D. P. Coster, R. Dux, C. Fuchs, G. Haas,
A. Herrmann, L. D. Horton, A. Kallenbach, M. Kaufmann,
C. Konz, V. Kotov, A. S. Kukushkin, K. Lackner, H. W. Müller,
J. Neuhauser, R. Pungo, M. Reich, D. Reiter, W. Schneider
and ASDEX Upgrade Team: Critical issues identified by the
comparison between experiment and SOLPS modelling on
ASDEX Upgrade. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, TH/P6-15 (2007).
Coster, D. P., X. Bonnin, A. Chankin, G. Corrigan, W. Fundamenski,
L. Owen, T. Rognlien, S. Wiesen, R. Zagorski and JET-EFDA
Contributors: Benchmarking Tokamak Edge Modelling Codes.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-4.026 (2007).
Conway, G. D., J. Schirmer, C. Angioni, J. C. Fuchs, R. Dux,
F. Jenko, E. Holzhauer, S. Klenge, B. Kurzan, A. G. Peeters,
C. Maggi, E. Poli, M. Reich, F. Ryter, B. Scott, W. Suttrop,
C. Tröster, E. Wolfrum, H. Zohm and ASDEX Upgrade Team:
Study of turbulence and radial electric field transitions in ASDEX
Upgrade using Doppler reflectometry. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, EX/2-1 (2007).
Conway, G. D., C. Tröster, J. Schirmer, C. Angioni, E. Holzhauer,
F. Jenko, F. Merz, E. Poli, B. Scott, W. Suttrop and ASDEX
Upgrade Team: Doppler reflectometry on ASDEX Upgrade:
Foundations and latest results. 8 th International Reflectometry
Workshop (IRW8), Open Access, 30-36 (2007).
http://plasma.ioffe.ru/irw8/proceedings.html
Conway, G. D., C. Tröster, B. Scott, K. Hallatschek and ASDEX
Upgrade Team: Observations on Geodesic Acoustic Mode
scaling and core localization in ASDEX Upgrade using
Doppler reflectometry. 34 th European Physical Society
Conference on Plasma Physics. Contributed Papers, (Eds.)
P. Gasior, J. Wolowski. ECA 31 F. European Physical Society,
Geneva, O-4.009 (2007).
Publications
139
Da Graca, S., G. D. Conway, P. Lauber, M. Maraschek, D. Borba,
S. Günter, L. Cupido, K. Sassenberg, F. Serra, M. E. Manso,
CFN Reflectometry Group and ASDEX Upgrade Team:
Studies of fast particle modes in ASDEX Upgrade using
reflectometry and comparison with theoretical prediction.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-5,096 (2007).
Dinklage, A., H. Maaßberg, R. Preuss, Y. Turkin, H. Yamada,
E. Ascasibar, C. D. Beidler, J. H. Harris, A. Kus, S. Murakami,
S. Okamura, F. Sano, U. Stroth, Y. Suzuki, J. Talmadge,
V. Tribaldos, K. Y. Watanabe and A. Werner: Physical model
assessment of the energy confinement time scaling in stellarators.
Fusion Energy 2006, International Atomic Energy
Agency, Vienna, EX/P7-1 (2007).
Dodt, D., A. Dinklage, R. Fischer and R. Preuss: Assessment
of Electron Energy Distributions in Discharges by Optical Emission
Spectroscopy. Bayesian Inference and Maximum Entropy
Methods in Science and Engineering: 27 th International
Workshop on Bayesian Inference and Maximum Entropy
Methods in Science and Engineering. (Eds.) K. H. Knuth,
A. Caticha, J. L. Center, A. Giffin, C. C. Rodriguez. AIP Conference
Proceedings 954. American Institute of Physics,
Melville, NY, 468-475 (2007).
Doerner, R., M. Baldwin, G. Federici, J. Hanna, A. Loarte,
D. Nishijima, R. Pugno, J. Roth, K. Schmid, G. Tynan, A. Wiltner
and D. Whyte: Beryllium containing plasma interactions
with ITER materials. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, IT/P1-20 (2007).
Dux, R., R. Neu, V. Bobkov, H. Greuner, O. Gruber, C. Hopf,
A. Kallenbach, T. Pütterich, V. Rohde and ASDEX Upgrade
Team: Tungsten as first wall material in ASDEX Upgrade.
Fusion Energy 2006, International Atomic Energy Agency,
Vienna, EX/3-3Ra (2007).
Dux, R., R. Pugno, T. Pütterich, V. Bobkov, A. Kallenbach,
R. Neu and ASDEX Upgrade Team: Impurity Influx in the
All Tungsten ASDEX Upgrade. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-1.052 (2007).
Eich, T., A. Kallenbach, A. Herrmann, J. C. Fuchs, C. S. Chang,
D. Tskhakaya and ASDEX Upgrade Team: ELM divertor
heat load in forward and reversed field in ASDEX Upgrade.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-2.017
(2007).

Erckmann, V., P. Brand, H. Braune, G. Dammertz, G. Gantenbein,
W. Kasparek, H. P. Laqua, G. Michel, M. Schmid, M. Thumm,
M. Weißgerber, W7X ECRH Team at IPP Greifswald, W7-X
Team at FZK Karlsruhe and W7-X Team at IPF Stuttgart: The
W7-X ECRH Plant: Recent Achievements. Radio Frequency
Power in Plasmas: 17 th Topical Conference on Radio Frequency
Power in Plasmas. (Eds.) P. M. Ryan, D. A. Rasmussen. AIP
Conference Proceedings 933. American Institute of Physics,
Melville, NY, 421-424 (2007).
Erckmann, V., P. Brand, H. Braune, G. Dammertz, G. Gantenbein,
W. Kasparek, H. P. Laqua, G. Michel, M. Thumm, M. Weißgerber,
W7-X ECRH Team at IPP Greifswald, W7-X ECRH Team at
FZK Karlsruhe and W7-X ECRH Team at IPF Stuttgart: The
140 GHz, 10 MW, CW ECRH Plant for W7-X: A Training
Field for ITER. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, IT/2-4Rd (2007).
Fable, E., C. Angioni, A. Bottino, S. Brunner, T. Dannert,
F. Jenko and O. Sauter: The role of electron-driven microinstabilities
in particle transport during electron Internal Transport
Barriers. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.100 (2007).
Feist, J. H. and Project Team W7-X: Status of Wendelstein
7-X construction. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior,
J. Wolowski. ECA 31 F. European Physical Society, Geneva,
P-1.161 (2007).
Fischer, R., E. Wolfrum, J. Schweinzer and ASDEX Upgrade
Team: Probabilistic Lithium beam data analysis. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-5.077 (2007).
Franzen, P., H. D. Falter, U. Fantz, W. Kraus, M. Berger,
S. Christ, M. Fröschle, R. Gutser, B. Heinemann, S. Hilbert,
S. Leyer, A. Lümkemann, C. Martens, P. McNeely, R. Riedl,
E. Speth and D. Wünderlich: Progress of the Development
of the IPP RF Negative Ion Source for the ITER Neutral
Beam System. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, IT/2-3Rc (2007).
Franzen, P., U. Fantz, W. Kraus, M. Berger, S. Christ-Koch,
M. Fröschle, B. Heinemann, F. Maisberger, C. Martens,
P. McNeely, R. Riedl, E. Speth, D. Wünderlich and T. Zacharias:
Homogeneity and long pulse operation of the IPP RF source
for the ITER NBI system. 34 th European Physical Society
Conference on Plasma Physics. Contributed Papers, (Eds.)
P. Gasior, J. Wolowski. ECA 31 F. European Physical Society,
Geneva, P-4.182 (2007).
Publications
140
Frank, D. and T. Soddemann: Interoperable Job Submission
and Management with GridSAM, JMEA and UNICORE.
German e-Science (GeS) Conference. Max Planck Digital
Library, München (2007).
http://www.ges2007.de
Gal, K., P. T. Lang, J. Neuhauser and ASDEX Upgrade Team:
Pellet Induced Perturbations in the Plasma Edge. 34 th European
Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-4.080 (2007).
Gantenbein, G., S. Alberti, A. Arnold, G. Dammertz, V. Erckmann,
E. Giguet, R. Heidinger, J. P. Hogge, S. Illy, W. Kasparek,
H. P. Laqua, F. Legrand, W. Leonhardt, C. Liévin, G. Michel,
G. Neffe, B. Piosczyk, M. Schmid, M. Thumm and M. Q. Tran:
Experimental results of the 1-MW,140-GHz, CW Gyrotron
for W7-X. Fusion Energy 2006, International Atomic Energy
Agency, Vienna, IT/2-4Re (2007).
Gantenbein, G., H. Braune, G. Dammertz, S. Alberti, V. Erckmann,
J. P. Hogge, S. Illy, W. Kasparek, H. P. Laqua, F. Legrand,
W. Leonhardt, C. Liévin, G. Michel, G. Neffe, F. Noke,
B. Piosczyk, F. Purps, M. Schmid, M. Thumm and M. Q. Tran:
High-power experiments with 140 GHz series gyrotrons for W7-X.
Proceedings of the 8 th IEEE International Vacuum Electronics
Conference. IEEE Operation Center, Piscataway, NJ, 41-42
(2007).
Gantenbein, G., G. Dammertz, V. Erckmann, S. Illy, W. Kasparek,
C. Lechte, F. Legrand, G. Lietaer, C. Liévin, B. Piosczyk,
M. Schmid and M. Thumm: Experimental results on highpower
gyrotrons for the stellarator W7-X. Conference Digest
of the 32 nd International Conference on Infrared and Millimeter
Waves, and 15 th International Conference on Terahertz
Electronics, IEEE Operation Center, Piscataway, NJ, CD-ROM,
102-103 (2007).
Giannone, L., W. Schneider, P. J. McCarthy, A. C. C. Sips,
W. Treutterer, J. C. Fuchs, J. Stober and ASDEX Upgrade
Team: Real time magnetic flux surface positions for ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.113
(2007).
Gobbin, M., P. Martin, L. Marrelli, H.-U. Fahrbach, M. Garcia-
Munoz, S. Günter, V. Igochine, M. Maraschek, M. Reich,
R. B. White and AUG Team: Numerical study of fast ions
transport induced by MHD instabilities in the tokamak. 34 th
European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-4.073 (2007).

Groth, M., N. H. Brooks, D. P. Coster, R. Dux, M. E. Fenstermacher,
R. J. Groebner, J. Harhausen, A. Kallenbach, C. J. Lasnier,
A. W. Leonard, W. H. Meyer, H. W. Müller, T. H. Osborne,
M. Reich, G. D. Porter, R. Pugno, M. E. Rensink, D.L. Rudakov,
M. Tsalas, J. G. Watkins, M. Wischmeier, E. Wolfrum, ASDEX
Upgrade Team and DIII-D Team: Effect of Divertor
Geometry on Fueling Profile of the Core Plasma in Low-
Density, Ohmic Plasmas in ASDEX Upgrade and DIII-D.
34 th European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-1.039 (2007).
Gruber, O. and ASDEX Upgrade Team: Overview of ASDEX
Upgrade results. Invited paper. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, OV/2-2 (2007).
Günter, S., G. Conway, C. Forest, H.-U. Fahrbach, M. Garcia
Munoz, S. da Graca, T. Hauff, J. Hobirk, V. Igochine, F. Jenko,
K. Lackner, P. Lauber, P. McCarthy, M. Maraschek, P. Martin,
E. Poli, K. Sassenberg, E. Strumberger, G. Tardini, H. Zohm
and ASDEX Upgrade Team: Fast Particle Physics on ASDEX
Upgrade – Interaction of Energetic Particles with Large and
Small Scale Instabilities. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, EX/6-1 (2007).
Gulejova, B., R. A. Pitts, X. Bonnin, D. Coster, R. Behn,
J. Horacek, J. Marki and TCV Team: Time-dependent modelling
of ELMing H-mode at TCV with SOLPS5. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-1.044 (2007).
Haange, R. and W7-X Team: Experience Gained during Fabrication
and Construction of Wendelstein 7-X. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, FT/2-3 (2007).
Hallatschek, K.: News from the Geodesic Acoustic Mode:
Magnetic Shear-, q-, and Geometry Effect. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, TH/P2-6 (2007).
Harhausen, J., J. C. Fuchs, A. Kallenbach, W. Schustereder,
M. Wischmeier and ASDEX Upgrade Team: Interpretation
of H α Imaging Diagnostics Data on ASDEX Upgrade. 34 th
European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-2.037 (2007).
Hellsten, T., M. Laxaback, T. Bergkvist, T. Johnson, M. Mantsinen,
G. Matthews, F. Meo, F. Nguyen, J.-M. Noterdaeme, C. C. Petty,
T. Tala, D. Van Eester, P. Andrew, P. Beaumont, V. Bobkov,
M. Brix, J. Brzozowski, L.-G. Eriksson, C. Giroud, E. Joffrin,
V. Kiptily, J. Mailloux, M.-L. Mayoral, I. Monakhov, J. Ongena,
R. Sartori, A. Stäbler, E. Rachlew, E. Tennfors, A. Tuccillo,
Publications
141
A. Walden, K.-D. Zastrow and JET-EFDA Contributors:
Fast Wave Current Drive and Direct Electron Heating in JET
ITB Plasmas. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, EX/P6-2 (2007).
Herrmann, J. and T. Hamacher: Challenges and Opportunities
of an Interconnected European and Russian Electricity
Network. 9 th IAEE European Energy Conference. IAEE,
Cleveland, OH, CD-ROM, 1-8 (2007).
Hynönen, V., T. Kurki-Suoni, K. Sugiyama, R. Dux, A. Stäbler,
T. Ahlgren and ASDEX Upgrade Team: Fusion tritons and
plasma-facing components in a fusion reactor. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F. European
Physical Society, Geneva, P-4.034 (2007).
Jenko, F., C. Angioni, T. Dannert, F. Merz, A. G. Peeters and
P. Xanthopoulos: Microturbulence in magnetic fusion devices:
new insights from gyrokinetic simulation and theory. Fusion
Energy 2006, International Atomic Energy Agency, Vienna,
EX/8-5Ra (2007).
Kallenbach, A., A. Chankin, D. Coster, T. Eich, J. Harhausen,
A. Herrmann, B. Kurzan, H. W. Müller, E. Wolfrum, M. Wischmeier
and ASDEX Upgrade Team: Divertor characterisation and data
consistency in ASDEX Upgrade. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-1.063 (2007).
Kardaun, O., G. Becker, A. Kus, P. Lang, P. McCarthy, F. Ryter,
A. Stäbler, J. Stober and Confinement Database Working
Group: The tortuous route of confinement prediction near
Operational Boundary Improvement of analysis based on
ITERH.DB4/L.DB3 database. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, IT/P1-10 (2007).
Kasparek, W., M. Petelin, D. Shchegolkov, V. Erckmann,
B. Plaum, A. Bruschi and ECRH Groups at IPP, FZK and IPF:
The electron cyclotron heating system for the stellarator W7-X:
Status and recent achievements. Conference Digest of the 32 nd
International Conference on Infrared and Millimeter Waves,
and 15 th International Conference on Terahertz Electronics, IEEE
Operation Center, Piscataway, NJ, CD-ROM, 939-940 (2007).
Kasparek, W., M. Petelin, D. Shchegolkov, V. Erckmann,
B. Plaum, A. Bruschi and ECRH Groups at IPP, FZK and IPF:
FaDiS, a Fast Switch and Combiner for High-power Millimetre
Wave Beams. Conference Digest of the 32 nd International
Conference on Infrared and Millimeter Waves, and
15 th International Conference on Terahertz Electronics, IEEE
Operation Center, Piscataway, NJ, CD-ROM, 389-390 (2007).

Kirschner, A., V. Philipps, M. Balden, X. Bonnin, S. Brezinsek,
J. P. Coad, D. Coster, S. K. Erents, H. G. Esser, W. Fundamenski,
A. Huber, J. Likonen, H. Maier, G. F. Matthews, M. Mayer,
R. A. Pitts, M. Rödig, M. J. Rubel, U. Samm, J. D. Strachan,
M. Wischmeier and JET-EFDA Contributors: Material
Erosion and Redeposition during the JET MkIIGB-SRP
Divertor Campaign. Invited paper. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, EX/3-5 (2007).
Konz, C., L. D. Horton, E. Strumberger, S. Günter, P. J. McCarthy,
G. T. A. Huysmans, P. B. Snyder and ASDEX Upgrade Team:
The Peeling-Ballooning Model Revisited. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F. European
Physical Society, Geneva, P-4.067 (2007).
Krychowiak, M., P. Mertens, B. Schweer, S. Brezinsek, R. König,
O. Schmitz, M. Brix, T. Klinger and U. Samm: LIF measurements
on an atomic helium beam in the edge of a fusion plasma.
34 th European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-2.142 (2007).
Kukushkin, A. S., H. D. Pacher, V. Kotov, D. Reiter, D. Coster,
G. W. Pacher and H. P. Zehrfeld: Optimisation of the Shape of the
ITER Divertor dome. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.061 (2007).
Kurzan, B., M. Gemisic-Adamov, L. D. Horton, H. Meister,
H. Murmann, J. Neuhauser, W. Suttrop and ASDEX Upgrade Team:
Analysis of large and small scale flucuations in the plasma edge
of ASDEX Upgrade. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.031 (2007).
Lang, P. T., B. Alper, R. Buttery, K. Gal, J. Hobirk, J. Neuhauser,
M. Stamp and JET EFDA Contributors: ELM triggering by
local pellet perturbations at JET. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-5.132 (2007).
Lederer, H., R. Hatzky, R. Tisma, A. Bottino and F. Jenko:
Hyperscaling of Plasma Turbulence Simulations in DEISA.
Proceedings of the HPDC 2007 Conference & Co-Located
Workshops, CLADE ’07. ACM, New York, NY, p. 19 ff. (2007).
Lipschultz, B., N. Asakura, X. Bonnin, D. Coster, G. Counsell,
R. Doerner, R. Dux, G. Federici, M. Fenstermacher, W. Fundamenski,
P. Ghendrih, A. Herrmann, J. Hu, A. Kallenbach, S. Krasheninnikov,
K. Krieger, G. Kirnev, A. Kreter, A. Kukushkin, V. Kurnaev,
B. LaBombard, J. Li, S. Lisgo, A. Loarte, T. Nakano, R. Neu,
Publications
142
N. Ohno, H. Pacher, J. Paley, Y. Pan, G. Pautasso, V. Philipps,
V. Riccardo, V. Rohde, J. Roth, D. Rudakov, P. Stangeby,
S. Takamura, T. Tanabe, E. Tsitrone, D. Whyte, Y. Yang and S. Zhu:
Plasma-surface interaction, scrape-off layer and divertor physics:
Implications for ITER. Invited paper. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, IT/1-4 (2007).
Loarer, T., C. Brosset, J. Bucalossi, P. Coad, G. Esser, J. Hogan,
J. Likonen, M. Mayer, P. Morgan, V. Philipps, V. Rohde, J. Roth,
M. Rubel, E. Tsitrone and JET EFDA Contributors: Gas Balance
and Fuel Retention in Fusion Devices. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, EX/3-6 (2007).
Lunt, T., G. Fußmann and O. Waldmann: The ion velocity
distribution in front of a neutralizing target. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F. European
Physical Society, Geneva, P-1.043 (2007).
Maggi, C. F., R. J. Groebner, N. Oyama, R. Sartori, L. D. Horton,
A. C. C. Sips, W. Suttrop, ASDEX Upgrade Team, T. Leonard,
T. C. Luce, M. R. Wade, DIIII-D-Team, Y. Kamada, H. Urano,
JT-60U Team, Y. Andrew, C. Giroud, E. Joffrin, E. de la Luna
and EFDA-JET Contributors: Characteristics of the H-mode
pedestal improved confinement scenarios in ASDEX Upgrade,
DIII-D, JET and JT-60U. Invited paper. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, IT/P1-6 (2007).
Maier, H., T. Hirai, M. Rubel, R. Neu, P. Mertens, H. Greuner,
C. Hopf, G. Matthews, O. Neubauer, G. Piazza, E. Gauthier,
J. Likonen, R. Mitteau, G. Maddaluno, B. Riccardi, V. Philipps,
C. Ruset, C. Lungu and JET EFDA Contributors: Tungsten
and Beryllium Armour Development for the JET ITER-like
Wall Project. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, IT/P2-4 (2007).
Marushchenko, N. B., V. Erckmann, H. Maaßberg and Y. Turkin:
Analysis of ECCD scenarios for different configurations of the
W7-X Stellarator. 34 th European Physical Society Conference on
Plasma Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-5.129 (2007).
McCarthy, P. J., C. B. Forest, M. Foley, L. Giannone, O. Gruber,
J. Hobirk, L. D. Horton, K. Lackner, P. Martin, M. Reich,
W. Schneider, A. C. C. Sips and ASDEX Upgrade Team:
Plasma geometry and current profile identification on ASDEX
Upgrade using an integrated equilibrium generation and
interpretation system. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, TH/P3-7 (2007).
Medvedev, S. Yu, A. A. Ivanov, A. A. Martynov, Yu. Yu. Poshekhonov,
S. H. Kim, J. B. Lister, Y. R. Martin, O. Sauter, L. Villiard and
P. T. Lang: Edge stability and boundary shaping in tokamaks.

34 th European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-4.078 (2007).
Merkel, P.: Feedback stabilization of resistive wall modes in
the presence of multiply-connected wall structures. Fusion
Energy 2006, International Atomic Energy Agency, Vienna,
TH/P3-8 (2007).
Müller, H. W., A. V. Chankin, B. Kurzan, M. Maraschek,
J. Neuhauser, V. Rohde, A. Schmid, M. Tsalas, M. Wischmeier
and ASDEX Upgrade Team: Parallel plasma flow and radial
electric field in the scrape-off layer of ASDEX Upgrade.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.060 (2007).
Na, Y.-S., J.-G. Kwak, J. Y. Kim, J.-M. Noterdaeme, B. H. Park
and A. C. C. Sips: Modelling of ICRH-heated Ramp-up
Phases at ASDEX Upgrade in KSTAR Experimental Conditions.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-5.147 (2007).
Nemov, V. V., S. V. Kasilov, W. Kernbichler, B. Seiwald,
Y. Suzuki and J. Geiger: Calculations of on effective ripple
for a stellarator magnetic field computed by the HINT2
code. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-4.063 (2007).
Neuhauser, J., V. Bobkov, A. Chankin, D. P. Coster, R. Dux,
T. Eich, L. Fattorini, M. Garcia-Munoz, J. Harhausen, A. Herrmann,
L. Horton, A. Kallenbach, S. Kalvin, A. Kirk, B. Koch,
G. Kocsis, B. Kurzan, P. Lang, M. Maraschek, H. W. Müller,
H. D. Murmann, R. Neu, M. Reich, V. Rohde, A. Schmid,
W. Suttrop, M. Tsalas, M. Wischmeier, E. Wolfrum and ASDEX
Upgrade Team: Structure and Dynamics of Spontaneous and
Induced ELMs on ASDEX Upgrade. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, EX/P8-2 (2007).
Nührenberg, C., S. R. Hudson and A. H. Boozer: Verification
of the CAS3D-perturbed equilibrium code in the cylindrical
limit. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-4.065
(2007).
Ongena, J., J. Mailloux, Y. Baranov, L. Bertalot, C. D. Callis,
G. Corrigan, A. Ekedahl, K. Erents, L.-G. Eriksson, M. Goniche,
T. Hellsten, I. Jenkins, T. Johnson, D. L. Keeling, V. Kiptily,
P. U. Lamalle, M. Laxaback, E. Lerche, M. J. Mantsinen,
M.-L. Mayoral, J.-M. Noterdaeme, V. Parail, V. Petrizilka,
Publications
143
S. Popovichev, A. Salmi, M. Santala, J. Spence, S. Sharapov,
A. A. Tuccillo, D. Van Eester and EFDA-JET Contributors:
Recent progress in JET on Heating and Current Drive studies
in view of ITER. Fusion Energy 2006, International Atomic
Energy Agency, Vienna, EX/P6-9 (2007).
Pautasso, G., C. J. Fuchs, O. Gruber, A. Herrmann, K. Lackner,
C. F. Maggi, M. Maraschek, T. Pütterich, E. Wolfrum and
ASDEX Upgrade Team: Plasma shut-down with fast impurity
puff on ASDEX Upgrade. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, EX/P8-7 (2007).
Pautasso, G., J. C. Fuchs, O. Gruber, A. Gude, V. Igochine,
K. Mark, V. Rohde, M. Beck, P. Cierpka, G. Prausner,
C. Wittmann, ASDEX Upgrade Team, C. Linz, J. Simon,
J. Weiser and V. Galazky: Recent results on disruptions mitigation
with a new fast valve. 34 th European Physical Society
Conference on Plasma Physics. Contributed Papers, (Eds.)
P. Gasior, J. Wolowski. ECA 31 F. European Physical Society,
Geneva, P-5.151 (2007).
Pereverzev, G. V.: Asymptotic description of high frequency
eigenmodes in tokamak. 34 th European Physical Society
Conference on Plasma Physics. Contributed Papers, (Eds.)
P. Gasior, J. Wolowski. ECA 31 F. European Physical Society,
Geneva, P-5.061 (2007).
Pereverzev, G. V., S. Günter, K. Lackner and E. Strumberger:
Transport and stability study of a fusion power plant scenario.
Fusion Energy 2006, International Atomic Energy Agency,
Vienna, FT/P5-23 (2007).
Piosczyk, B., G. Dammertz, A. Arnold, G. Gantenbein, S. Illy,
J. Jin, O. Prinz, J. Flamm, T. Rzesnicki, M. Thumm, S. Alberti,
T. Goodmann, J. P. Hogge, M. Q. Tran, V. Erckmann, H. Laqua,
G. Michel, O. Dumbrajs, P. Benin, E. Giguet and C. Lievin:
Development of High Power Gyrotrons for Fusion Applications
at FZK. IEEE Pulsed Power and Plasma Science Conference
(ICOPS 2007). CD-ROM, Albuquerque, NM, 551 (2007).
Piovesan, P., V. Igochine, P. Lauber, K. Sassenberg, A. Flaws,
M. Garcia-Munoz, S. Günter, M. Maraschek, L. Marrelli,
P. Martin, P. McCarty and AUG Team: TAE internal structure
through high-resolution soft x-ray measurements in ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.139 (2007).
Preuss, R., A. Dinklage, A. Weller and W7-AS Team: Assessment
of confinement scaling models for W7-AS high-ß data.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-2.054 (2007).

Preuss, R. and U. von Toussaint: Comparison of numerical
methods for evidence calculation. Bayesian Inference and
Maximum Entropy Methods in Science and Engineering:
27 th International Workshop on Bayesian Inference and Maximum
Entropy Methods in Science and Engineering. (Eds.)
K. H. Knuth, A. Caticha, J. L. Center, A. Giffin, C. C. Rodriguez.
AIP Conference Proceedings 954. American Institute of
Physics, Melville, NY, 221-228 (2007).
Pütterich, T., R. Neu, R. Dux and ASDEX Upgrade Team:
Spectroscopic Diagnostic of Tungsten in Fusion Plasmas.
34 th European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-5.103 (2007).
Rambadt, M., R. Breu, L. Clementi, T. Fieseler, A. Gieseler,
W. Gürich, P. Malfetti, R. Menday, J. Reetz and A. Streit:
DEISA and D-Grid: using UNICORE in production Grid
infrastructures. German e-Science (GeS) Conference. Max-
Planck-Digital Library, München (2007).
http://www.ges2007.de
Reetz, J., T. Soddemann, B. Heupers and J. Wolfrat: Accounting
Facilities in the European Supercomputing Grid DEISA.
German e-Science (GeS) Conference. Max-Planck-Digital
Library, München (2007).
http://www.ges2007.de
Reich, M., M. Brix, V. Kiptily, S. D. Pinches, A. Werner and
JET-EFDA Contributors: Particle loss signatures during
sawtooth events at JET. 34 th European Physical Society
Conference on Plasma Physics. Contributed Papers, (Eds.)
P. Gasior, J. Wolowski. ECA 31 F. European Physical Society,
Geneva, O-4.016 (2007).
Reich, M., P. McCarthy, J. Hobirk and ASDEX Upgrade Team:
Calibration methods for the MSE diagnostic at ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-2.127
(2007).
Reiman, A., M. C. Zarnstorff, D. Monticello, J. Krommes,
A. Weller, J. Geiger and W7-AS Team: Localized Breaking
of Flux Surfaces and the Equilibrium β Limit in the W7AS
Stellarator. Fusion Energy 2006, International Atomic Energy
Agency, Vienna, TH/P7-3 (2007).
Ribeiro, T. T., B. Scott and F. Serra: Self consistent MHD
equilibrium in turbulence simulations. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-4.055 (2007).
Publications
144
Rohde, V., V. Mertens, T. Loarer and ASDEX Upgrade Team:
Gas balance in high density discharges at ASDEX Upgrade.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-2.030 (2007).
Ryter, F., G. Tardini, L. D. Horton, W. Schneider, W. Suttrop,
R. Fischer, N. Hicks, P. J. McCarthy, A. Stäbler, J. Stober,
E. Wolfrum and ASDEX Upgrade Team: Experimental determination
of the NBI power deposition and consequences for NBI
current drive. 34 th European Physical Society Conference on
Plasma Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.140 (2007).
Rzesnicki, T., B. Piosczyk, G. Dammertz, G. Gantenbein,
M. Thumm and G. Michel: 170 GHz, 2 MW coaxial cavity
gyrotron – investigation of the parasitic oscillations and efficiency
of the RF-output system. Proceedings of the 8 th IEEE
International Vacuum Electronics Conference. IEEE Operation
Center, Piscataway, NJ, 45-46 (2007).
Schirmer, J., C. Maggi, H. Zohm, R. Dux, A. Flaws, M. Maraschek,
A. Peeters, K. Sassenberg, A. Scarabosio, L. Urso and ASDEX
Upgrade Team: Rotation frequencies of MHD modes in ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.133 (2007).
Schmid, A., A. Hermann, A. Kirk, J. Neuhauser, S. Günter,
H. W. Müller, M. Maraschek, V. Rohde and ASDEX Upgrade Team:
Characterization of Type-I ELM Induced Filaments in ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.026 (2007).
Schmid, K., T. Schwarz-Selinger, W. Jacob, R. Dux and ASDEX
Upgrade Team: The implications of high-Z first wall materials
on noble gas wall recycling. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, EX/3-3Rb (2007).
Schneider, R.: Plasma-wall interaction: how atomic processes
influence the performance of fusion plasmas. Atomic Processes
in Plasmas: The 15 th International Conference on Atomic Processes
in Plasmas. (Eds.) J. D. Gillaspy, J. J. Curry, W. L. Wiese.
AIP Conference Proceedings 926. American Institute of
Physics, Melville, NY, 45-55 (2007).
Schrittwieser, R., A. Kendl, S. Konzett, C. Ionita, F. Mehlmann,
P. Balan, V. Naulin, J. J. Rasmussen, A. H. Nielsen, O. E. Garcia,
H. W. Müller, A. Herrmann, V. Rohde, M. Maraschek and
ASDEX Upgrade Team: Experimental and numerical characterisation
of fluctuations in the SOL of ASDEX Upgrade
during L-mode and ELMy H-mode. 34 th European Physical

Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-1.125 (2007).
Schustereder, W., A. Herrmann, K. Krieger, V. Rohde and
ASDEX Upgrade Team: Impurity fluxes in the scrape-off
layer of ASDEX Upgrade in the full tungsten wall configuration.
34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-2.034 (2007).
Scott, B., A. Kendl, D. Reiser, T. Ribeiro and D. Strinzi:
Studies of the tokamak edge with self consistent turbulence,
equilibrium, and flows. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, TH/1-1 (2007).
Sips, A. C. C., C. Forest, O. Gruber, P. J. McCarthy, O. Kardaun,
V. Mertens, A. Peeters, G. V. Pereverzev, A. Stäbler, J. Stober,
G. Tardini and ASDEX Upgrade Team: The performance of
improved H-modes at ASDEX Upgrade and projection to
ITER. Fusion Energy 2006, International Atomic Energy
Agency, Vienna, EX/1-1 (2007).
Stober, J., V. Bobkov, C. Forest, O. Gruber, J. Hobirk, L. D. Horton,
C.F. Maggi, M. Maraschek, P. Martin, V. Mertens, Y.-S. Na,
M. Reich, A. C. C. Sips, A. Stäbler, G. Tardini, H. Zohm,
P. McCarthy and ASDEX Upgrade Team: Physics studies of
the improved H-mode scenario in ASDEX Upgrade. Fusion
Energy 2006, International Atomic Energy Agency, Vienna,
EX/P1-7 (2007).
Stober, J., A. Gude, F. Leuterer, A. Manini, R. Neu, T. Pütterich,
A. C. C. Sips, D. Wagner, H. Zohm and ASDEX Upgrade Team:
First experiments with the extended ECRH system on ASDEX
Upgrade. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-5.138 (2007).
Suttrop, W., T. Bertoncelli, V. Bobkov, O. Gruber, A. Herrmann,
P. Merkel, M. Rott, M. Sempf, U. Seidel, B. Streibel, E. Strumberger,
T. Vierle, D. Yadikin, Q. Yu and ASDEX Upgrade Team: Active
in-vessel coils and a conducting wall for MHD control in
ASDEX Upgrade. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior,
J. Wolowski. ECA 31 F. European Physical Society, Geneva,
P-5.119 (2007).
Suttrop, W., L. D. Horton, C. Konz, B. Kurzan, C. F. Maggi,
H. Meister, J. Neuhauser, A. C. C. Sips, U. Urano, E. Wolfrum
and ASDEX Upgrade Team: Studies of the edge pedestal and
behaviour of edge localised modes in improved H-mode and
small-ELM regimes in ASDEX Upgrade. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, EX/P8-5 (2007).
Publications
145
Szepesi, T., S. Kalvin, G. Kocsis, P. T. Lang and ASDEX Upgrade
Team: Radial acceleration of solid hydrogen pellets in hot
tokamak plasmas. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior,
J. Wolowski. ECA 31 F. European Physical Society, Geneva,
P-4.037 (2007).
Tardini, G., L. D. Horton, O. Kardaun, C. F. Maggi, A. G. Peeters,
G. V. Pereverzev, A. C. C. Sips, J. Stober and ASDEX Upgrade
Team: Extrapolation of ASDEX Upgrade H-mode discharges
to ITER. 34 th European Physical Society Conference on Plasma
Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.090 (2007).
Toi, K., F. Watanabe, S. Ohdachi, K. Narihara, T. Morisaki,
S. Sakakibara, X. Gao, M. Goto, K. Ida, M. Kobayashi, S. Masuzaki,
J. Miyazawa, S. Morita, K. Tanaka, T. Tokuzawa, K. W. Watanabe,
A. Weller, L. Yan, M. Yoshinuma, K. Kawahata, A. Komori and
LHD Experimental Group: Characteristic Features of Edge
Transport Barrier Formed in Helical Divertor Configuration
of the Large Helical Device. Fusion Energy 2006, International
Atomic Energy Agency, Vienna, EX/P1-13 (2007).
Tröster, C., G. D. Conway, W. Suttrop, J. Schirmer, H. Zohm
and ASDEX Upgrade Team: Density fluctuation measurements
with fast-sweep X-mode reflectometry. 8 th International
Reflectometry Workshop (IRW8), Open Access, 80-84 (2007).
http://plasma.ioffe.ru/irw8/proceedings.html
Waldmann, O., G. Fußmann and W. Bohmeyer: Ion mass
spectrometry in a magnetized plasma. 34 th European Physical
Society Conference on Plasma Physics. Contributed Papers,
(Eds.) P. Gasior, J. Wolowski. ECA 31 F. European Physical
Society, Geneva, P-5.108 (2007).
Weisen, H., C. Angioni, A. Zabolotsky, M. Maslov, M. Beurskens,
C. Fuchs, L. Garzotti, C. Giroud, B. Kurzan, P. Mantica, D. Mazon,
M. E. Puiatti, K.-D. Zastrow, JET-EFDA Work Programme,
ASDEX Upgrade Team and TCV Team: Peaked density profiles
in low collisionality H-modes in JET, ASDEX Upgrade
and TCV. Fusion Energy 2006, International Atomic Energy
Agency, Vienna, EX/8-4 (2007).
Weller, A., A. Werner, J. Geiger, C. Nührenberg, H. Thomsen
and W7-AS Team: Multi-Harmonic Modes in W7-AS High-Beta
Configurations. 34 th European Physical Society Conference on
Plasma Physics. Contributed Papers, (Eds.) P. Gasior, J. Wolowski.
ECA 31 F. European Physical Society, Geneva, P-1.112 (2007).
Werner, A., A. Dinklage, G. Kühner, H. Maaßberg, J. Schacht,
J. Svensson, U. von Toussaint and Y. Turkin: Integrated Software
Development for Wendelstein 7-X. Fusion Energy 2006,
International Atomic Energy Agency, Vienna, FT/P7-6 (2007).

Wischmeier, M., D. Coster, A. Chankin, C. Fuchs, M. Groth,
J. Harhausern, A. Kallenbach, H. W. Müller, M. Tsalas and
ASDEX Upgrade Team: Simulating divertor detachment of
ohmic discharges in ASDEX Upgrade using SOLPS: the
role of Carbon. 34 th European Physical Society Conference
on Plasma Physics. Contributed Papers, (Eds.) P. Gasior,
J. Wolowski. ECA 31 F. European Physical Society, Geneva,
P-1.040 (2007).
Wittenburg, P., D. Broeder, M. Kemps-Snijders, A. Dimitriadis
and T. Soddemann: A Federation of Language Archives
Enabling Future eHumanitaies Scenarios. German e-Science
(GeS) Conference. Max Planck Digital Library, München
(2007).
http://www.ges2007.de
Wolfrum, E., D. Coster, C. Konz, M. Reich and ASDEX Upgrade
Team: Edge ion temperature gradients in H-mode discharges.
34 th European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-2.039 (2007).
Wünderlich, D., R. Gutser, U. Fantz, M. Berger, S. Christ-
Koch, H. D. Falter, P. Franzen, M. Fröschle, B. Heinemann,
W. Kraus, C. Martens, P. McNeely, R. Riedl and E. Speth:
Modeling of a Negative Ion RF Source for ITER NBI. 34 th
European Physical Society Conference on Plasma Physics.
Contributed Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F.
European Physical Society, Geneva, P-1.149 (2007).
Yokoyama, M., H. Maaßberg, K. Ida, C. Beidler, F. Castejon,
T. Estrada, A. Fujisawa, T. Minami, T. Shimozuma, Y. Takeiri,
V. Tribaldos, A. Dinklage, S. Murakami and H. Yamada:
Core Electron-Root Confinement (CERC) in Helical Plasmas.
Fusion Energy 2006, International Atomic Energy Agency,
Vienna, EX/5-3 (2007).
Yu, Q.: Theoretical Studies on the Physics of Magnetic Islands.
Fusion Energy 2006, International Atomic Energy Agency,
Vienna, TH/P3-13 (2007).
Zhang, D., L. Giannone, B. Klein and W7-X Team: The
Bolometry Concept for the W7-X Stellarator. 34 th European
Physical Society Conference on Plasma Physics. Contributed
Papers, (Eds.) P. Gasior, J. Wolowski. ECA 31 F. European
Physical Society, Geneva, P-5.111 (2007).
Zohm, H., S. Cirant, G. Gantenbein, S. Günter, F. Leuterer,
A. Manini, M. Maraschek, L. Urso, Q. Yu and ASDEX
Upgrade Team: Control of MHD instabilities by ECCD:
ASDEX Upgrade results and implications for ITER. Fusion
Energy 2006, International Atomic Energy Agency, Vienna,
EX/4-1Rb (2007).
Publications
146
Thesis
Boosch, S.: Optimierung der Montageplanung für die regulären
Stutzen des Wendelstein 7-X, Erstellung eines Quality
Assurance and Assembly Plans (QAAP’s). Fachhochschule
Stralsund (2007).
Botzenhart, F.: Optimale Nutzung von Solarenergie unter
thermodynamischen Aspekten und wirtschaftlichem Kalkül.
Universität Augsburg (2007).
Cwiklinski, A.: Wechselwirkung zwischen Stickstoff und
Kohlenstoff in magnetisierten Plasmen. Freie Universität
und Humboldt-Universität Berlin (2007).
Hertkorn, T.: Nichtlineare Triaden Wechselwirkungen in
zweidimensionaler Turbulenz. Universität Bayreuth
(2007).
Köppl, S.: Charakterisierung und Hochtemperaturoxidation
von W-Legierungen. Technische Universität München
(2007).
Krüger, M.: Konzept zur Nutzung von Biogas zur Wärmeund
Elektroenergieerzeugung in der Hansestadt Greifswald.
Hochschule Wismar (2007).
Kuckahn, A.: Untersuchung der Übertragungsstrecke von
den Messsensoren unter den extremen Bedingungen eines
Kernfusionsexperiments. Fachhochschule Coburg (2007).
Langer, B.: Bestimmung des radialen elektrischen Feldes
am Plasmarand durch linienintegrierte Messungen an He+.
Technische Universität München (2007).
Leonard, V.: Scada System for the Stellarator W7-X.
Technical University Gdánsk (2007).
Mechel, J.: Untersuchung der Biegebelastbarkeit von Aluminiumschweißnähten
am Mantel eines Supraleiters. Fachhochschule
Stralsund (2007).
Schmuck, S.: Designstudien für die Thomson-Streuung von
Wendelstein 7-X. Ernst-Moritz-Arndt-Universität Greifswald
(2007).
Seidel, R.: Röntgenspektroskopie hochgeladener Wolfram-
Ionen. Humboldt-Universität Berlin (2007).
Versteegh, A.: Analysis of a Longliving Atmospheric Plasmoid.
Technische Universität Eindhoven und Humboldt-Universität
Berlin (2007).

Wigger, C.: Entwicklung eines Codes zum Test von Gleichgewichten
gegen axisymmetrische Instabilitäten im Tokamak.
Ludwig-Maximilians-Universität München (2007).
Zimmerer, H.: Evaluation of sequence comparison methods
for metagenomics. Eberhard-Karls-Universität Tübingen
(2007).
PhD-Thesis
Allen, F. I.: Electron Capture by Highly Charged Ions from
Surfaces and Gases. Humboldt-Universität Berlin (2007).
Barth, S.: Untersuchung des Interatomaren Coulomb-Zerfalls
in schwach gebundenen Systemen. Technische Universität
Berlin (2007).
Bizyukov, I.: Sputtering and surface modification of tungsten
layers by bombardment with deuterium and carbon ion beams.
V. N. Karazin Kharkiv National University, Kharkiv (2007).
Dreier, H.: Bayesian Experimental Design – Applications in
Nuclear Fusion. Ernst-Moritz-Arndt-Universität Greifswald
(2007).
Köck, T.: Herstellung und Charakterisierung eines SiC/Cu-
Metall-Matrix-Verbundwerkstoffes mit angepasster Faser/
Matrix-Grenzfläche. Technische Universität München (2007).
Krychowiak, M.: Laser-induced fluorescence of atomic helium
beams in a fusion edge plasma. Ernst-Moritz-Arndt-Universität
Greifswald (2007).
Skandera, D.: Statistical Properties and Structure of Turbulent
Convection. Technische Universität München (2007).
Ulrich, V.: Untersuchung von Autoionisationsprozessen in
kleinen Molekülen und Clustern mittels hochauflösender
Elektronenkoinzidenzspektroskopie. Technische Universität
Berlin (2007).
Windisch, T.: Intermittent events and structure propagation in
plasma turbulence. Ernst-Moritz-Arndt-Universität Greifswald
(2007).
Habilitation
Naujoks, D.: Plasma-Surface Interaction in Controlled Fusion.
Humboldt-Universität Berlin (2007).
Publications
147
Patents
Brockmann, R.: Doppellagentechnik. Erfindungsmeldung:
1.02.2007. Inanspruchnahme als Know-how: 16.05.2007.
Brockmann, R.: Leckortung innerhalb einer begehbaren
Prüfkammer. Erfindungsmeldung: 19.01.2007. Inanspruchnahme
als Know-how: 16.05.2007.
Brockmann, R.: Verfahren und Vorrichtung zur Leckprüfung.
Keine Auslandsanmeldungen: 26.02.2007.
Brockmann, R.: Verfahren zur Vermeidung von Porenbildung
beim Schweißen von Werkstoffen. Erfindungsmeldung:
10.10.2007. Inanspruchnahme als Know-how: 18.12.2007.
Erckmann, V., G. Dammertz and M. Schmid: Method and
Apparatus for collector sweeping control of an electron
beam. Erfindungsmeldung vom 12.03.2007. Gemeinsame
Anmeldung mit FZK: 5.05.2007.
Schauer, F.: Stromzuführungseinrichtung. Einleitung der
nationalen und regionalen Phasen der PCT-Anmeldung:
1.06.2007.
Schauer, F. and M. Nagel: Thermischer Schild. Freigabe der
Anmeldung: 13.03.2007.
Scholz, T.: Verbesserte Potentialtrenner. Erfindungsmeldung:
13.06.2007. Freigabe der Erfindung: 26.07.2007.
Sihler, C.: Verfahren und Dämpfungsvorrichtung zur Dämpfung
einer Torsionsschwingung in einem rotierenden Antriebsstrang.
Erweiterung der Anmeldung auf Hongkong:
19.01.2007.
Wanner, M.: Sicherheitseinrichtung mit geringem Ansprechdruck
für Vakuumbehälter mit hohen Dichtheitsanforderungen.
Keine Auslandsanmeldungen: 31.07.2007.

Laboratory Reports
Internal IPP Reports
IPP 4/286
Gutser, R., D. Wünderlich, U. Fantz and P. Franzen: Rechnungen
zur Extraktion negativer Wasserstoffionen aus einem
HF-Plasma. 145 p. (2007).
IPP5/119
Dimova, K. and R. Meyer-Spasche: On a Moving Boundary
Model of Anomalous Heat Transport in a Tokamak Plasma.
18 p. (2007).
IPP 10/33
Berger, M. and U. Fantz: Cavity-Ringdown-Spektroskopie
an Wasserstoff-Niederdruckplasmen. 93 p. (2007).
IPP 12/3
Eckstein, W., R. Dohmen, A. Mutzke and R. Schneider:
SDTrimSP: A Monte Carlo Code for Calculating Collision
Phenomena in Randomized Targets. 40 p. (2007).
IPP 13/6
Krychowiak, M.: Laser-induced fluorescence of atomic helium
beams in a fusion edge plasma. 177 p. (2007).
IPP 13/7
Schmuck, S.: Designstudien für die Thomson-Streuung von
Wendelstein 7-X. 92 p. (2007).
IPP 13/8
Dreier, H.: Bayesian Experimental Design – Applications in
Nuclear Fusion. 143 p. (2007).
IPP 16/12
Barth, S.: Untersuchung des Interatomaren Coulomb-Zerfalls
in schwach gebundenen Systemen. 133 p. (2007).
IPP 16/13
Tosato, G. C.: Lehren aus globalen Energieszenarien; Global
long-term energy scenarios: lessons learnt. 83 p. (2007).
IPP 16/14
Hamacher, T., S. Winkelmüller and J. Kuckelkorn: Energiekonzept
für das Konversionsgelände Sheridan-Kaserne in
Augsburg. 101 p. (2007).
IPP 16/16
Krüger, M.: Konzept zur Nutzung von Biogas zur Wärmeund
Elektroenergieerzeugung in der Hansestadt Greifswald.
Hochschule Wismar. 134 p. (2007).
Publications
148
IPP 16/17
Botzenhart, F.: Optimale Nutzung von Solarenergie unter
thermodynamischen Aspekten und wirtschaftlichem Kalkül.
221 p. (2007).
External Reports
Nuorkivi, A., N. Killström, P. Saarnia, E. Tähti, J. Markovitch,
G. Naumov and T. Hamacher: Energy. Future. Responsibility.
– Promoting Energy Saving and Corporate Social
Responsibility in the Baltic Sea Region. In: Publications of the
Uusimaa Regional Council C 59. Uusimaa Regional Council,
Helsinki Region, 63 p. (2007).
NIFS-874
Preuss, R., H. Yamada, M. Osakabe, S. Sakakibara, K.
Tanaka, K.Y. Watanabe and A. Dinklage: Determination of
uncertainties in the machine variables of LHD and CHS for
confinement time scaling. National Institute of Fusion
Science (NIFS), Oroshi-cho, Toki-shi, Gifu-ken, 8 p. (2007).

Adelhelm, C., M. Balden, E. Cochran and S. Denis: Protection
of carbon films against chemical erosion by doping with
transition metals. (E-MRS Spring Meeting, Symposium Q:
Protective Coatings and Thin Films, 2007-05-28 to 2007-06-01,
Strasbourg).
Adelhelm, C., M. Balden, M. Rinke and M. Stüber: Influence
of metal-doping and annealing on the structure of amorphous
carbon films. (17 th International Vacuum Congress (IVC-17),
13 th International Conference on Surface Science (ICSS-13),
International Conference on Nano Science and Technology
(ICN+T 2007), 2007-07-02 to 2007-07-06, Stockholm).
Adelhelm, C., M. Balden, P. Starke, A. Centeno, C. Blanco,
I. Lopez Galilea and C. Garcia-Rosales: Deuterium ion beam
and plasma exposure experiments of metal-doped carbon
materials relevant for fusion applications. (European Congress
and Exhibition on Advanced Materials and Processes
(EUROMAT 2007), 2007-09-10 to 2007-09-13, Nürnberg).
Allmaier, K., C. D. Beidler, M. Yu. Isaev, S. V. Kasilov,
W. Kernbichler, H. Maaßberg, S. Murakami, V. V. Nemov,
D. A. Spong and V. Tribaldos: ICNTS – Benchmarking of Bootstrap
Current Coefficients. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Angelino, P., V. Grandgirard, Y. Sarazin, G. Dif-Pradalier,
S. Jolliet, A. Bottino, X. Garbet, P. Ghendrih, B. McMillan,
T. M. Tran and L. Villard: Benchmark of a semi-Lagrangian
and a Lagrangian code for gyrokinetic simulations. (12 th US-
EU Transport Taskforce Workshop (TTF-12), 2007-04-17 to
2007-04-20, San Diego, CA).
Angelino, P., V. Grandgirard, Y. Sarazin, G. Dif-Pradalier,
S. Jolliet, A. Bottino, X. Garbet, P. Ghendrih, B. McMillan,
T.M. Tran and L. Villard: Effects of plasma elongation on Geodesic
Acoustic Modes. (International Sherwood Fusion Theory
Conference, 2007-04-23 to 2007-04-25, Annapolis, MD).
Antar, G. Y., E. Wolfrum, M. Tsala, D. P. Coster, C. Konz,
H. W. Müller, J. Neuhauser, V. Rohde, B. Scott, M. Wischmeier
and ASDEX Upgrade Team: The Statistical Properties of
Turbulence in the Scrape-off Layer of Upper-Single Null H
and L-mode plasmas. (34 th EPS Conference on Plasma
Physics, 2007-07-02 to 2007-07-06, Warsaw).
Arnold, A., O. Prinz, D. Wagner and M. Thumm: Operation
of a quasioptical multi-mode generator for 105-150 GHz.
(32 nd International Conference on Infrared and Millimeter Waves
and the 15 th International Conference on Terahertz Electronics
(IRMMW-THz 2007), 2007-09-02 to 2007-09-07, Cardiff).
Lectures
149
Ascasibar, E., D. López-Bruna, F. Castejón, V. Tribaldos,
H. Maaßberg, C. D. Beidler, R. Brakel, A. Dinklage, J. Geiger,
J. H. Harris, A. Kus, T. Mizuuchi, S. Murakami, S. Okamura,
R. Preuss, F. Sano, U. Stroth, Y. Suzuki, J. Talmadge, Y. Turkin,
K. Y. Watanabe, A. Weller, A. Werner, H. Yamada and M. Yokoyama:
Effect of rotational transform and shear on confinement.
(Joint Conference of 17 th International Toki Conference on
Physics of Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to
2007-10-19, Ceratopia Toki, Gifu).
Assas, S., L.-G. Eriksson, J.-M. Noterdaeme, C. Maggi, J. Schirmer
and G. Conway: Toroidal plasma rotation with minimal
momentum input in ICRF only heated ASDEX Upgrade
plasmas. (17 th Topical Conference on Radio Frequency Power
in Plasmas, 2007-05-07 to 2007-05-09, Clearwater, FL).
Balden, M., C. Adelhelm, M. Sikora and M. Rasinski: Röntgenabsorptionsspektroskopie
an Nano-kristallinen a-C:Me Filmen
(X-ray absorption spectroscopy on nano-crystalline a-C:Me
films). (2. FA-Sitzung “Strahllinien”, 2007-11-09, Technische
Universität Garching).
Balden, M., C. Adelhelm, P. Starke, I. Lopez Galilea, C. Garcia-
Rosales, A. Centeno, C. Blanco, J. Ramos Fernandez and
M. Martinez Escandell: Erosion of metal-doped carbon materials
by hydrogen. (13 th International Conference on Fusion
Reactor Materials (ICFRM-13), 2007-12-10 to 2007-12-14,
Nice).
Baldzuhn, J., H. Ehmler, L. Genini, K. Hertel, A. Hölting,
C. Sborchia and T. Schild: Cold Tests of the Superconducting
Coils for the Stellarator W7-X. (Conference on Magnet Technology,
MT-20, 2007-08-27 to 2007-08-31, Philadelphia, PA).
Baudach, M., W. Bohmeyer, D. Naujoks, A. Markin and
A. Cwiklinski: Zersetzung, Bildung und Transport von Kohlenwasserstoffen.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Behler, K., H. Blank, H. Eixenberger, A. Lohs, K. Lüddecke,
R. Merkel, G. Raupp, G. Schramm, W. Treutterer, M. Zilker and
ASDEX Upgrade Team: Real-Time Diagnostics at ASDEX
Upgrade – Architecture and Operation. (6 th IAEA Technical
Meeting on Control, Data Acquisition, and Remote Participation
for Fusion Research, 2007-06-04 to 2007-06-08,
Inuyama).
Behringer, K.: Aktuelle Fragen der Plasmaphysik. (WS 2006/
2007, SS 2007. Seminar, Universität Augsburg).
Behringer, K.: Spektroskopie von Nichtgleichgewichtsplasmen.
(SS 2007. Vorlesung, Universität Augsburg).

Behringer, K.: Spektroskopische Diagnostik eines gepulsten
Lichtbogenplasmas. (Berliner Seminar über Plasmaphysik,
2007-06-05, Humboldt-Universität Berlin).
Behringer, K. and U. Fantz: Physikalisches Praktikum für
Fortgeschrittene, Teil B. (WS 2006/2007, SS 2007. Universität
Augsburg).
Behringer, K., U. Fantz and T. Hamacher: Probleme der
zukünftigen Energieversorgung. (WS 2006/2007, SS 2007.
Seminar, Universität Augsburg).
Behringer, K., U. Fantz and M. Schreck: Anwendungen und
Diagnostik von Niederdruckplasmen. (SS 2007. Vorlesung,
Universität Augsburg).
Behringer, K. and T. Höschen: Spektroskopische Diagnostik
eines gepulsten Bogens zur Partikelsynthese. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Behringer, K., M. Stritzker, U. Fantz and M. Schreck:
Diagnostik von Niederdruckplasmen als industrielle Schlüsseltechnologie.
(SS 2007. Seminar, Universität Augsburg).
Behrisch, R. and W. Eckstein: Sputtering by particle bombardement.
(Ion Surface Interaction Conference (ISI-2007),
2007-08-24 to 2007-08-27, Svenigorod).
Beidler, C. D., J. Geiger, H. Maaßberg, N. B. Marushchenko,
Y. Turkin and W7-AS Team: Transport Modeling for W7-X
on the Basis of W7-AS Experimental Results. (Joint Conference
of 17 th International Toki Conference on Physics of
Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to 2007-10-19,
Ceratopia Toki, Gifu).
Beidler, C. D., M. Yu. Isaev, S. V. Kasilov, W. Kernbichler,
H. Maaßberg, S. Murakami, V. V. Nemov, D. A. Spong and V.
Tribaldus: ICNTS – Impact of Incompressible E×B Flow in
Estimating Mono-Energetic Transport Coefficients. (Joint
Conference of 17 th International Toki Conference on Physics
of Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to 2007-10-19,
Ceratopia Toki, Gifu).
Beidler, C. D., M. Y. Isaev, S. V. Kasilov, W. Kernbichler,
H. Maaßberg, S. Murakami, V. V. Nemov, D. A. Spong,
V. Tribaldus and G. O. Leitold: ICNTS – Benchmarking of
Momentans Correction Techniques. (Joint Conference of
17 th International Toki Conference on Physics of Flows and
Turbulence in Plasmas and 16 th International Stellarator/
Heliotron Workshop, 2007-10-15 to 2007-10-19, Ceratopia
Toki, Gifu).
Lectures
150
Berger, M., S. Christ-Koch, U. Fantz and NNBI Team:
Diagnostics of H - Densities in RF-driven Ion Sources for
Fusion Applications. (12 th International Conference on Ion
Sources (ICIS), 2007-08-26 to 2007-08-31, Jeju, Korea).
Biedermann, C.: The Berlin EBIT project and fusion relevant
spectroscopy. (PEARL 2007: Physics at EBIT and Advanced
Research Light Sources, 2007-03-08 to 2007-03-12, Fudan,
Shanghai).
Biedermann, C., F. Allen, R. Radtke and G. Fußmann: Charge
exchange of highly charged argon ions inside EBIT and with
an external gas target. (10 th International Symposium on the
Physics and Applications of Electron Beam Ion Sources and
Traps (EBIS/T 2007), 2007-08-01 to 2007-08-04, Heidelberg).
Bobkov, V.: Specific aspects of the ASDEX Upgrade (AUG)
ICRF system. Implications and suggestions for JET and
ITER. (ICRF Meetings 2007 (TFH/JET-ITER/EnTicE/EFDA
Coordination Task Meeting), 2007-04-16 to 2007-04-20,
Schloss Ringberg, Tegernsee).
Bobkov, V., F. Braun, R. Dux, A. Herrmann, A. Kallenbach,
R. Neu, J.-M. Noterdaeme, Th. Pütterich and ASDEX Upgrade
Team: Tungsten sputtering during ICRF in ASDEX Upgrade.
(17 th Topical Conference on Radio Frequency Power in Plasmas,
2007-05-07 to 2007-05-09, Clearwater, FL).
Bolt, H.: Cross cutting European research on materials for extreme
environments. (13 th International Conference on Fusion
Reactor Materials (ICFRM-13), 2007-12-10 to 2007-12-14, Nice).
Bolt, H.: Materialforschung für den Fusionsreaktor. (DGM
Fachausschusssitzung “Metallische Verbundwerkstoffe und
zelluläre Metalle”, 2007-11-06, Garching).
Bolt, H.: Materialfragen in der Kernfusion. (Studentenkolloqium,
2007-05-16, Universität Clausthal-Zellerfeld).
Bolt, H.: Materials challenges for the plasma-facing components
of fusion reactors. (Kolloqiumsvortrag, 2007-02-22,
University of Oxford).
Bolt, H.: New materials for extreme conditions. (EU Workshop
on Basic Research and Innovative Science for Energy
(BRISE), 2007-05-24, Brussels).
Bolt, H.: Outline of a fusion materials CSA. (EFDA Fusion
Materials Workshop, 2007-03-02, Garching).
Bolt, H.: Wolfram als plasmabelastetes Material für Fusionsanlagen.
(Kolloqiumsvortrag, 2007-01-12, Forschungszentrum
Karlsruhe).

Bolt, H. and M. Balden: Oberflächentechnologie (OT). (SS 2007.
Vorlesung, Technische Universität München).
Bolt, H., M. Balden, A. Brendel, F. Koch, D. Levchuk, H. Maier,
K. Ertl, J. Roth, A. Wiltner, F. Kost and K. Schmid: Neue
Materialien für den Einsatz unter extremen Anforderungen
in der Kernfusion. (ISC-Seminar, 2007-02-02, Fraunhofer-
Institut für Silicatforschung, Würzburg).
Bolt, H. and J. You: Dünne Schichten. (WS 2006/2007.
Vorlesung, Technische Universität München).
Bongers, W. A., M. F. Graswinckel, M. A. Van den Berg,
A. Bruschi, I. Danilov, A. J. H. Donne, B. S. Q. Elzendoorn,
A. P. H. Goede, R. Heidinger, M. A. Henderson, O. G. Kruijt,
B. Kruizinga, N. Lopes Cardozo, A. Moro, E. Poli, D. M. S. Ronden
and A. G. A. Verhoeven: Recent developments of the Upper
port ECH&CD Launcher systems for ITER based on the
Remote Steering concept. (4 th IAEA Technical Meeting on
ECRH Physics and Technology for ITER, 2007-06-06 to
2007-06-08, Vienna).
Bosch, H.-S.: Kernfusion – Was wir von den Sternen für
unsere Energieversorgung lernen können. (Schulvortrag der
MPG-Hauptversammlung 2007, 2007-06-26, Kiel).
Bottino, A., S. Jolliet, A. G. Peeters and R. Hatzky: Global
low noise particle simulations of ETG and ITG turbulence.
(US-Japan Joint Institute for Fusion Theory (JIFT) Workshop,
2007-01-10, San Diego, CA).
Bovshuk, V. R., W. A. Cooper, M. I. Mikhailov, J. Nührenberg
and V. D. Shafranov: Search for very-high-beta MHD stable
quasi-isodynamic configurations. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki,
Gifu).
Bradshaw, A. M.: Energy research: short term needs and long
term strategy. (The 3 rd Transatlantic Market Conference –
Growth & Security: Energy and Energy Transportation,
2007-05-13 to 2007-05-15, Washington, D.C.).
Bradshaw, A. M.: Fusion Energy: Bringing the Sun Down to
Earth, the Real Challenge of the 21 st Century. (Sustainable
Neighbourhood 4 th BMBF Forum for Sustainability 2007,
2007-05-08 to 2007-05-10, Leipzig).
Bradshaw, A. M.: The future of our energy supply: What comes
after fossil fuels? (Deutsch-Britische Gesellschaft, 2007-03-15,
Internationales Begegnungszentrum (IBZ), Garching).
Lectures
151
Bradshaw, A. M.: ITER – the way to fusion energy. (Seminar,
Physics Department Trinity College, 2007-03-02, Dublin).
Bradshaw, A. M.: ITER: Der Weg zur Fusionsenergie. (Collegium
Europaeum Jenense, 2007-12-05, Universität Jena).
Bradshaw, A. M.: ITER: Der Weg zur Fusionsenergie.
(Physikalisches Kolloquium, 2007-01-15, Universität Ulm).
Bradshaw, A. M.: ITER: Der Weg zur Fusionsenergie.
(Workshop des Graduiertenkollegs Hochenergiephysik und
Teilchenastrophysik, 2007-10-10, Freudenstadt).
Bradshaw, A. M.: Kernfusion als Energiequelle der Zukunft.
(Rheno-Franconia Dies Academicus, 2007-01-24, München).
Bradshaw, A. M.: Kernfusion als Energiequelle der Zukunft.
(Rotary Club Meeting, 2007-10-30, Gauting Würmtal).
Bradshaw, A. M.: Kernfusion: eine nachhaltige Energietechnologie.
(Energiegespräche Ossiach, 2007-06-13, Ossiach).
Bradshaw, A. M.: Nuclear fusion: An energy source for tomorrow.
(World Economic Forum Annual Meeting, 2007-01-24
to 2007-01-28, Davos).
Bradshaw, A. M.: Nuclear fusion and ITER for non-experts.
(Britisch Science Officers Conference, 2007-03-28 to 2007-03-30,
Berlin).
Bradshaw, A. M.: The roadmap for nuclear fusion. (The 15 th
International Conference on Vacuum Ultraviolet Radiation
Physics, 2007-07-29 to 2007-08-03, Berlin).
Bradshaw, A. M.: The roadmap for nuclear fusion. (Symposium
on Vacuum Based Science and Technology; Rudolf
Jaeckel-Preis 2007 der DVG, 2007-09-05 to 2007-09-07,
Greifswald).
Bradshaw, A. M.: Der Sonnen-Imitator. Neuer Plasma-
Modus kann die Energieausbeute des geplanten Fusionstestreaktors
ITER verdoppeln. (The Power of Ideas, 2007-06-07,
Kühlungsborn, Heiligendamm).
Brandt, C., O. Grulke and T. Klinger: Einfluss raumzeitlicher
elektrostatischer und elektromagnetischer Felder auf Driftwellen.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Braun, F.: Faraday shield RF modelling and RF sheath dissipation.
(ITER – ICH Working Group Meeting 8, 2007-01-11
to 2007-01-12, Cadarache).

Braun, F. and J.-M. Noterdaeme: Simulations of different
Faraday screen configurations for the ITER ICRH antenna.
(17 th Topical Conference on Radio Frequency Power in
Plasmas, 2007-05-07 to 2007-05-09, Clearwater, FL).
Braune, H., P. Brand, V. Erckmann, H. P. Laqua, L. Jonitz,
W. Leonhardt, D. Mellein, G. Michel, F. Noke, F. Purps,
K. H. Schlüter, M. Winkler and W7-X ECRH Teams at IPP,
IPF and FZK: Operation experiences with the HV-system
for the ECRH installation at W7-X. (19 th Joint Russian-
German Workshop on ECRH and Gyrotrons, 2007-07-18 to
2007-07-24, Garching).
Brendel, A., T. Köck and H. Bolt: Mechanical Properties of
SiC long fibre reinforced Copper. (13 th International Conference
on Fusion Reactor Materials (ICFRM-13), 2007-12-10
to 2007-12-14, Nice).
Brendel, A., T. Köck, T. Brendel and H. Bolt: SiC long fibre
reinforced copper for the divertor heat sink. (European Congress
and Exhibition on Advanced Materials and Processes
(EUROMAT 2007), 2007-09-10 to 2007-09-13, Nürnberg).
Bronold, F. X., K. Matyash, D. Tskhakaya, R. Schneider and
H. Fehske: Particle-in-cell Monte Carlo model for oxygen
discharges. (DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Buchner, C., R. Haller, E. Harmeyer, J. Mühlbacher, A. Wieczorek
and H. Wobig: Investigation on Power Supply Operation for
the Helias Stellarator Fusion Reactor. (EPE 2007 – 12 th European
Conference on Power Electronics and Applications,
2007-09-02 to 2007-09-05, Aalborg).
Buchner, C., E. Harmeyer, J. , A. Wieczorek and H. Wobig:
Investigation and Optimization on Auxiliary System Operation
of a Helias Fusion Reactor. (2007 IEEE International
Symposium on Industrial Electronics (ISIE 2007), 2007-06-04
to 2007-06-07, Vigo).
Bykov, V., F. Schauer, P. Eeten van and A. Tereshchenko:
Main Results and Critical Issues of W7-X Structural Analysis.
(22 nd Symposium on Fusion Engineering (SOFE 07),
2007-06-17 to 2007-06-21, Albuquerque, NM).
Cantarini, J., J. P. Knauer and E. Pasch: Design study of
the observation optics for the Thomson scattering system
planned at Wendelstein 7-X. (PLASMA 2007 – International
Conference on Research and Applications of Plasmas combined
with the 4 th German-Polish Conference on Plasma
Diagnostics for Fusion and Applications and the 6 th French-
Polish Seminar on Thermal Plasma in Space and Laboratory,
2007-10-16 to 2007-10-19, Greifswald).
Lectures
152
Cardella, A., L. Giordano, G. Crespi and T. Scholz: Development
of a Portable Reaming Tool for the Supporting
Structures of Wendelstein 7-X. (22 nd IEEE/NPSS Symposium
on Fusion Engineering, 2007-06-18 to 2007-06-22,
Albuquerque, NM).
Carvalho, P., H. Thomsen, S. Gori, U. von Toussaint, A. Weller,
R. Coelho, A. Neto, T. Pereira, C. Silva and H. Fernandes:
Fast tomographic methods on the tokamak ISTTOK. (PLASMA
2007 – International Conference on Research and Applications
of Plasmas combined with the 4 th German-Polish
Conference on Plasma Diagnostics for Fusion and Applications
and the 6 th French-Polish Seminar on Thermal
Plasma in Space and Laboratory, 2007-10-16 to 2007-10-19,
Greifswald).
Chauhana, N., S. Kamakshia, A. Kumara, A. Mittala, D. Wagner,
M. V. Kartikeyan and M. K. Thumm: Design and Optimization
of non-linear tapers for high power gyrotrons.
(22 nd National Symposium on Plasma Science & Technology
(PLASMA-2007), 2007-12-06 to 2007-12-10, Ahmedabad).
Christ-Koch, S., U. Fantz and NNBI Team: Ortsaufgelöste
Messung der negativen Wasserstoffionendichte in einer HF-
Quelle. (DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Colas, L., A. Ekedahl, M. Goniche, J. P. Gunn, B. Nold, Y. Corre,
M.-L. Mayoral, K. Kirov, J. Mailloux, S. Heuraux, E. Faudot,
V. Petrzilka, V. Bobkov, R. Dux, ASDEX Upgrade Team and
JET-EFDA Contributors: RF-induced modifications in the
scrape-off layer of magnetic fusion devices: a 2D spatial
structure. (34 th EPS Conference on Plasma Physics and
Controlled Fusion, 2007-07-02 to 2007-07-06, Warsaw).
Conway, G. D., C. Troester, J. Schirmer, C. Angioni, E. Holzhauer,
F. Jenko, F. Merz, E. Poli, B. Scott and W. Suttrop: Doppler
reflectometry on ASDEX Upgrade: Foundations and latest
results. (8 th International Reflectometry Workshop (IRW8),
2007-05-02 to 2007-05-04, St. Petersburg).
Counsell, G., P. Coad, J. A. Ferreira, M. Rubel, F. L. Tabares,
A. Widdowson, P. Sundelin, V. Philipps, G. Sergienko, D. Tafalla,
I. Tanarro, V. Herrero, C. Gomez-Aleixandre, J. M. Albella,
P. Gasior, J. Wolowski, J. Likonen, C. Grisolia, A. Semerok,
C. Hopf, W. Jacob, M. Schlüter, D. Farcage, D. Hole, T. Renvall
and P. Y. Thro: Progress with Tritium Removal and Mitigation
2006-7. (6 th Meeting of Contact Persons of the EU-PWI
Task Force, 2007-10-29 to 2007-10-31, Madrid).
Croari, G. and J. Baldzuhn: Acceptance Tests on the W7-X Coils.
(International Youth Conference on Energetics, 2007-05-31
to 2007-06-02, Budapest).

Cwiklinski, A., A. Markin, M. Baudach and W. Bohmeyer:
Interaction between Nitrogen and Hydrocarbons in Magnetized
Plasmas. (PLASMA 2007 – International Conference
on Research and Applications of Plasmas combined with the
4 th German-Polish Conference on Plasma Diagnostics for
Fusion and Applications and the 6 th French-Polish Seminar
on Thermal Plasma in Space and Laboratory, 2007-10-16 to
2007-10-19, Greifswald).
D’Inca, R., S. Assas, V. Bobkov, F. Braun, B. Eckert and
J.-M. Noterdaeme: Comparison of different arc detection methods
during plasma operations with ICRF heating on ASDEX
Upgrade. (17 th Topical Conference on Radio Frequency Power
in Plasmas, 2007-05-07 to 2007-05-09, Clearwater, FL).
Da Graça, S., G. Conway, P. Lauber, M. Maraschek, D. Borba,
S. Günter, L. Cupido, K. Sassenberg, F. Serra, M. E. Manso,
CFN Reflectometry Group and ASDEX Upgrade Team:
Localization of MHD and fast particle modes using reflectometry
in ASDEX Upgrade. (8 th International Reflectometry
Worskhop (IRW8), 2007-05-02 to 2007-05-04, St. Petersburg).
Dietrich, S., S. Christ, B. Crowley and U. Fantz: Electrical
probes for electron energy distribution function (EEDF)
measurements in low pressure hydrogen plasmas. (28 th International
Conference on Phenomena in Ionized Gases (ICPIG),
2007-07-15 to 2007-07-20, Prague).
Dietrich, S. and U. Fantz: Messung der Elektronendichte
mittels optischer Emissionsspektroskopie (OES) und Vergleich
mit anderen diagnostischen Methoden. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Dinklage, A., E. Ascasibar, C. D. Beidler, R. Brakel, R. Burhenn,
F. Castejon, T. Estrada, H. Funaba, Y. Feng, J. Geiger, J. H. Harris,
C. Hidalgo, K. Ida, M. Kobayashi, R. König, G. Kühner, A. Kus,
D. Lopez Bruna, H. Maaßberg, D. Mikkelsen, T. Mizuuchi,
N. Nakajima, R. Preuss, S. Sakakibara, F. Sano, F. Sardei,
U. Stroth, Y. Suzuki, J. Talmadge, H. Thomsen, B. P. Van Milligen,
K. Y. Watanabe, A. Weller, A. Werner, R. Wolf, H. Yamada
and M. Yokoyama: Status of the International Stellarator/
Heliotron Profile Database. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron Workshop,
2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Dinklage, A., B. Bruhn, H. Testrich and C. Wilke: Hysterese von
Ionisationswellen. (DPG AMOP-Frühjahrstagung, 2007-03-19
to 2007-03-23, Düsseldorf).
Dinklage, A., H. Dreier, R. Fischer, S. Gori, R. Preuss and
U. von Toussaint: Integrated data analysis for fusion: A
Lectures
153
Bayesian Tutorial for Diagnosticians. (International Workshop
on Burning Plasma Diagnostics, 2007-09-24 to 2007-09-28,
Varenna).
Dodt, D. and A. Dinklage: Effect of Uncertainties in a Collisional-Radiative
Model of a Gas Discharge. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Dodt, D., A. Dinklage, R. Fischer, K. Bartschat and O. Zatsarinny:
Form-Free Reconstruction of an Electron Energy Distribution
Function from Optical Emission Spectroscopy. (PLASMA
2007 – International Conference on Research and Applications
of Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Dodt, D., A. Dinklage, R. Fischer, K. Bartschat and O. Zatsarinny:
Integrated Data Analysis of Spectroscopic Data. (Joint Conference
of 17 th International Toki Conference on Physics of
Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to 2007-10-19,
Ceratopia Toki, Gifu).
Dodt, D., A. Dinklage, R. Fischer and R. Preuss: Spatially
Resolved Electron Energy Distributions of a Discharge
Plasma from Optical Emission Spectroscopy. (27 th International
Workshop on Bayesian Inference and Maximum
Entropy Methods in Science and Engineering, 2007-07-08
to 2007-07-13, New York, NY).
Dreier, H., A. Dinklage, R. Fischer, M. Hirsch and P. Kornejew:
Bayesian diagnostic design of a multichannel interferometer.
(34 th European Physical Society Conference on Plasma Physics,
2007-07-02 to 2007-07-06, Warsaw).
Dreier, H., A. Dinklage, R. Fischer, M. Hirsch and P. Kornejew:
Optimisation of the line of sight configuration of the multichannel
interferometer at Wendelstein 7-X. (PLASMA 2007 –
International Conference on Research and Applications of
Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Dreier, H., A. Dinklage and R. Preuss: Bayesian diagnostic
design of a multichannel interferometer. (17 th International
Toki Conference/16 th International Stellarator Workshop,
2007-10-15 to 2007-10-19, Toki).
Dreier, H., R. Preuss, A. Dinklage and V. Dose: Data adaptive
control parameter estimation for scaling laws. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).

Dreier, H., R. Preuss, A. Dinklage and V. Dose: Physical
data assessment for energy confinement scaling laws. (Joint
Conference of 17 th International Toki Conference on Physics
of Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to 2007-10-19,
Ceratopia Toki, Gifu).
Dumbrajs, O., V. Igochine and H. Zohm: Diffusion in a stochastic
magnetic field in ASDEX Upgrade. (Biennial Workshop
“Stochasticity in Fusion Plasmas” (SFP 2007), 2007-03-05
to 2007-03-07, Jülich).
Dux, R.: Impurities and exhaust with improved confinement.
(EPFW Meeting, 2007-12-03 to 2007-12-05, Prague).
Dux, R.: Plasmaphysik und Fusionsforschung. (SS 2007.
Proseminar, Technische Universität München, Garching).
Dux, R. and A. M. Bradshaw: Plasmaphysik und Fusionsforschung.
(SS 2007. Proseminar, Technische Universität
München, Garching).
Eckstein, W.: The Sputtering Yield. (Ion Surface Interaction
Conference (ISI-2007), 2007-08-24 to 2007-08-27, Svenigorod).
Eeten P. van, D. Hathiramani, V. Bykov and A. Cardella:
Design and test of the support elements of the W7-X superconducting
magnets. (22 nd Symposium on Fusion Engineering
(SOFE 07), 2007-06-17 to 2007-06-21, Albuquerque, NM).
Eich, T., A. Kallenbach, P. McCarthy, J. Neuhauser, G. Pautasso
and ASDEX Upgrade Team: In/Out power load asymmeries
during type-I ELMs in ASDEX Upgrade. (34 th EPS Conference
on Plasma Physics, 2007-07-02 to 2007-07-08, Warsaw).
Erckmann, V., P. Brand, H. Braune, G. Dammertz, G. Gantenbein,
W. Kasparek, H. P. Laqua, G. Michel, M. Schmid, M. Thumm,
M. Weißgerber, W7X ECRH Team at IPP Greifswald, W7-X
Team at FZK Karlsruhe and W7-X Team at IPF Stuttgart:
The W7-X ECRH Plant: Recent Achievements. (17 th Topical
Conference on Radio Frequency Power in Plasmas, 2007-05-07
to 2007-05-09, Clearwater, FL).
Erckmann, V., M. Schmid, H. P. Laqua, G. Dammertz, S. Illy,
H. Braune, F. Hollmann, F. Noke, F. Purps, ECRH Team at
IPP Greifswald, ECRH Team at FZK Karlsruhe and ECRH
Team at IPF Stuttgart: Advanced Gyrotron Collector Sweeping
with smooth Power Distribution. (4 th IAEA Technical Meeting
on ECRH Physics and Technology for ITER, 2007-06-06 to
2007-06-08, Vienna).
Evans, T. E., J. G. Watkins, I. Joseph, R. Moyer, J. Yu, M. Jakubowski
and O. Schmitz: 3D structures and dynamics of ELMs.
Lectures
154
(49 th Annual APS Division of Plasma Physics Meeting,
2007-11-12 to 2007-11-16, Orlando, FL).
Fantz, U.: Compilation, calculation and validaiton of fundamental
data for diatomic molecules. (CRP (Co-ordinated
Research Project) on “Atomic and Molecular Data for Plasma
Modelling”, 2007-06-18 to 2007-06-20, Vienna).
Fantz, U.: Diagnostik und Modellierung der NNBI Teststände
– wozu ? (IPP Summer University for Plasma Physics,
2007-09-24 to 2007-09-28, Greifswald).
Fantz, U.: Low pressure and high power RF sources for negative
hydrogen ions for fusion applications (ITER NBI). (12 th International
Conference on Ion Sources (ICIS), 2007-08-26 to
2007-08-31, Jeju).
Fantz, U.: Neutral beam injection for present and future
fusion devices. (IPP Summer University for Plasma Physics,
2007-09-24 to 2007-09-28, Greifswald).
Fantz, U.: Neutral beam injection for present and future
fusion devices. (Seminar, 2007-11-12 to 2007-11-16, Schloss
Ringberg, Tegernsee).
Fantz, U.: Regenbogen, Blitze und Polarlichter. (Lange
Nacht der Wissenschaft, 2007-10-13, Garching).
Fantz, U.: Plasma homogeneity of large RF sources: spectroscopy
and probes at IPP testbeds. (International CCNB
Meeting, 2007-05-22 to 2007-05-24, Culham).
Fantz, U.: Plasmaphysik und Fusionsforschung I. (WS 2006/
2007. Vorlesung, Universität Augsburg).
Fantz, U.: Plasmaphysik und Fusionsforschung II. (SS 2007.
Vorlesung, Universität Augsburg).
Fantz, U., P. Franzen, H. D. Falter, W. Kraus, M. Berger,
S. Christ-Koch, M. Fröschle, R. Gutser, B. Heinemann, S. Leyer,
C. Martens, P. McNeely, R. Riedl, E. Speth and D. Wünderlich:
Development of a Negative Ion RF Source for ITER NBI.
(34 th EPS Conference on Plasma Physics, 2007-07-02 to
2007-07-06, Warsaw).
Fantz, U., P. Franzen, H. D. Falter, W. Kraus, M. Berger,
S. Christ-Koch, M. Fröschle, R. Gutser, B. Heinemann,
C. Martens, P. McNeely, R. Riedl, E. Speth and D. Wünderlich:
Large low pressure, high power RF sources for negative hdyrogen
ions for fusion applications. (28 th International Conference
on Phenomena in Ionized Gases (ICPIG), 2007-07-15 to
2007-07-20, Prague).

Fantz, U., P. Franzen, H. D. Falter, W. Kraus, M. Berger,
S. Christ-Koch, M. Fröschle, R. Gutser, B. Heinemann,
C. Martens, P. McNeely, R. Riedl, E. Speth and D. Wünderlich:
Low Pressure and High Power RF Sources for Negative
Hydrogen Ions for Fusion Applications (ITER NBI). (International
Conference on Ion Sources (ICIS), 2007-08-26 to
2007-08-31, Jeju, Korea).
Feketeova, L., S. Feil, V. Grill, N. Endstrasser, B. Rasul,
W. Schustereder, A. Bacher, S. Matt-Leubner, F. Zappa, P. Scheier
and T. Märk: Elementary plasma reactions revisited: Electron
ionization and ion surface reactions relevant for fusion
plasmas. (16 th Symposium on Applications of Plasma Processes
(SAPP XVI), 2007-01-20 to 2007-01-25, Podbanské).
Feng, Y., M. Kobayashi, N. Ashikawa, L. Giannone, R. König,
LHD Experimental Group, S. Masuzaki, K. McCormick,
J. Miyazawa, T. Morisaki, S. Morita, O. Motojima, Y. Nakamura,
K. Narihara, N. Ohyabu, B. J. Peterson, F. Sardei, K. Sato, M. Shoji,
N. Tamura, H. Thomsen, M. Tokitani, F. Wagner, U. Wenzel,
H. Yamada and I. Yamada: Comparative Divertor-Transport
Study for W7-AS and LHD. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Fernandez, A., D. Wagner, A. Cappa, G. Müller and A. Tolkachev:
EC waves polarization control in the TJ-II, IRMMW-THz
2007. (32 nd International Conference on Infrared and Millimeter
Waves and the 15 th International Conference on Terahertz
Electronics (IRMMW-THz 2007), 2007-09-02 to
2007-09-07, Cardiff).
Fischer, R.: Integrated Data Analysis of Complementary
Experiments. (27 th International Workshop on Bayesian
Inference and Maximum Entropy Methods in Science and
Engineering (MaxEnt 2007), 2007-07-08 to 2007-07-13,
Saratoga Springs, NY).
Fischer, R. and A. Dinklage: The concept of integrated data
analysis of complementary experiments. (27 th International
Workshop on Bayesian Inference and Maximum Entropy Methods
in Science and Engineering (MaxEnt 2007), 2007-07-08
to 2007-07-13, Saratoga Springs, NY).
Flaws, A., A. Gude, V. Igochine, C. Maggi, M. Maraschek
and H. Zohm: The Role of Magneto-Hydrodynamic Instabilities
in the Improved H-Mode Scenario. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Franzen, P.: Status and Plans of the RF source development
at IPP Garching. (Coordinating Committee on Neutral Beams
(CCNB-Meeting), 2007-05-22 to 2007-05-24, Culham).
Lectures
155
Frerichs, H., D. Harting, D. Reiter and Y. Feng: Numerical
investigation of impurity transport in the ergodized edge
plasma at TEXTOR-DED. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Fröschle, M., B. Heinemann, R. Riedl, A. Stäbler and E. Speth:
Progress in the Development of High Heat Flux Panels for NBI in
AUG. (CCNB – Combined ITER Design and R&D Review and
Co-ordination Meeting, 2007-11-28 to 2007-12-01, Ahmedabad).
Funaba, H., A. Dinklage, H. Yamada, M. Yokoyama, K. Watanabe,
K. Narihara, I. Yamada, K. Tanaka, T. Tokuzawa, S. Murakami,
M. Osakabe, K. Kawahata and LHD Experimental Group:
Data structure for LHD plasmas in the international profile
database. (Joint Conference of 17 th International Toki Conference
on Physics of Flows and Turbulence in Plasmas and
16 th International Stellarator/Heliotron Workshop, 2007-10-15
to 2007-10-19, Ceratopia Toki, Gifu).
Fußmann, G.: Einführung in die Plasmaphysik. (WS 2006/2007.
Vorlesung, Humboldt-Universität Berlin).
Fußmann, G.: Kugelblitze, gibt es sie? (Greifswalder Physikalisches
Kolloquium, 2007-07-19, Universität Greifswald).
Fußmann, G.: Kugelblitze, gibt es sie? (Physikalisches Kolloquium,
2007-07-09, Ruhr-Universität Bochum).
Fußmann, G.: Plasmaphysik und Fusionsforschung. (SS 2007.
Vorlesung, Humboldt-Universität Berlin).
Fußmann, G.: Spektroskopische Analyse von Fusionsplasmen.
(108. Jahrestagung der Deutschen Gesellschaft für
Angewandte Optik, 2007-05-29 to 2007-06-02, Heringsdorf).
Fußmann, G., B. Jüttner, S. Noack and A. Versteegh: Ball
lightning – an old puzzle revisited. (PLASMA 2007 – International
Conference on Research and Applications of Plasmas
combined with the 4 th German-Polish Conference on Plasma
Diagnostics for Fusion and Applications and the 6 th French-
Polish Seminar on Thermal Plasma in Space and Laboratory,
2007-10-16 to 2007-10-19, Greifswald).
Gantenbein, G., H. Braune, G. Dammertz, V. Erckmann, S. Illy,
W. Kasparek, H. P. Laqua, C. Lechte, F. Legrand, C. Lievin,
W. Leonhardt, G. Michel, F. Noke, B. Piosczyk, F. Purps, M. Schmid
and M. Thumm: 1 MW, 140 GHz, CW gyrotron for W7-X.
Status report on series gyrotrons. (19 th Joint Russian-German
Workshop on ECRH and Gyrotrons, 2007-07-18 to 2007-07-24,
Karlsruhe/Stuttgart/Garching).
Garcia-Munoz, M., H.-U. Fahrbach, H. Zohm, J. Neuhauser,
M. Maraschek, S. Günter, P. Martin, K. Sassenberg and

V. Igochine: MHD induced fast ion losses in ASDEX Upgrade.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Garcia-Rosales, C., I. Lopez, N. Ordas, C. Adelhelm, M. Balden,
S. Lindig, G. Pintsuk, M. Grattarola and C. Gualco: Ti-doped
isotropic graphite for plasma facing components. (European
Congress and Exhibition on Advanced Materials and Processes
(EUROMAT 2007), 2007-09-10 to 2007-09-13, Nürnberg).
Garcia-Rosales, C., I. Lopez-Galilea, N. Ordas, C. Adelhelm,
M. Balden, S. Lindig, G. Pintsuk, M. Grattarola and C. Gualco:
Ti-doped isotropic graphite for plasma facing components.
(13 th International Conference on Fusion Reactor Materials
(ICFRM-13), 2007-12-10 to 2007-12-14, Nice).
Geiger, J.: Stability analysis of Wendelstein 7-X configurations
with increased mirror ratio. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Giannone, L.: Real time measurements for tokamak control.
(12. Anwender- und Technologiekongress “VIP 2007”,
2007-10-10 to 2007-10-11, Fürstenfeldbruck).
Golubeva, A., Y. Gasparyan, M. Mayer and J. Roth: A new
set-up for investigation of hydrogen ion driven permeation.
(18 th International Conference on Ion-Surface Interactions,
2007-08-24 to 2007-08-28, Zvenigorod).
Golubeva, A., M. Mayer and J. Roth: A new set-up for investigation
of hydrogen ion driven permeation. (3 rd International
Workshop “Interaction of Hydrogen Isotopes with Structural
Materials”, 2007-07-02 to 2007-07-07, St. Petersburg).
Greiche, A., W. Biel, R. Wolf and R. Burhenn: Absolute
Intensitätskalibrierung des XUV/VUV Übersichts-Spektrometersystems
HEXOS für Wendelstein 7-X. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Greuner, H. and B. Böswirth: Results of HHF tests of W7-X
target elements – the influence of degradation of heat transfer.
(ITER Divertor Meeting, 2007-11-07 to 2007-11-09, Barcelona).
Greuner, H., B. Böswirth, J. Boscary, P. Chaudhuri, J. Schlosser,
T. Friedrich, A. Plankensteiner and R. Tivey: Cyclic Heat Load
Testing of Improved CFC/Cu Bonding for the W7-X Divertor
Targets. (13 th International Conference on Fusion Reactor
Materials (ICFRM-13), 2007-12-10 to 2007-12-14, Nice).
Greuner, H., B. Böswirth, J. Boscary, A. Plankensteiner,
B. Schedler and R. Tivey: Testing of improved CFC/Cu
Lectures
156
Bondings for the W7-X Divertor Targets. (13 th International
Conference on Fusion Reactor Materials (ICFRM-13),
2007-12-10 to 2007-12-14, Nice).
Grote, H., J. Kißlinger, H. Greuner, B. Streibl and O. Volzke:
Vacuum Systems at Wendelstein 7-X. (Symposium on Vacuum
based Science and Technology, 2007-09-05 to 2007-09-07,
Greifswald).
Gruber, O.: ASDEX Upgrade Technical Systems. (Southwestern
Institute of Physics (SWIP), 2007-10-15, Chengdu).
Gruber, O. and ASDEX Upgrade Team: ASDEX Upgrade:
Status and Planning for 2008. (ASDEX Upgrade Programme
Committee Meeting, 2007-12-11, Garching).
Gruber, O. and ASDEX Upgrade Team: Recent results on
ASDEX Upgrade. (Southwestern Institute of Physics (SWIP),
2007-10-15, Chengdu).
Gruber, O., J. Schweinzer and H. Zohm: Extension of ASDEX
Upgrade Operation (action A10/I). (ASDEX Upgrade Programme
Committee Meeting, 2007-12-11, Garching).
Grulke, O.: Struktur der Materie für Umweltwissenschaftler.
(SS 2007. Vorlesung, Universität Greifswald).
Grulke, O., T. Windisch, V. Naulin and T. Klinger: Propagation
turbulenter Strukturen in Driftwellenturbulenz. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Günter, S.: Einführung in die Plasmaphysik. (WS 2006/2007.
Vorlesung, Technische Universität München).
Gurbich, A., I. Bogdanovic-Radovic, M. Chiari, C. Jeynes,
M. Kokkoris, A. Ramos, M. Mayer, E. Rauhala, O. Schwerer,
Shi Liqun and I. Vickridge: Status of the Problem of Nuclear
Cross Section Data for IBA. (18 th International Conference
on Ion Beam Analysis, 2007-09-23 to 2007-09-28, Hyderabad).
Gusev, V. K., V. K. Alimov, I. I. Arkhipov, M. Balden, E. A. Denisov,
A. E. Gorodetsky, A. A. Kurdumov, T. N. Kompaniec, V. M. Lebedev,
N. V. Litunovstkii, I. V. Mazul, A. N. Novokhatsky, Y. V. Petrov,
N. V. Sakharov, V. M. Sharapov, E. I. Terukov, I. N. Trapeznikova,
J. Roth, A. P. Zakharov and R. K. Zalavutdinov: Recrystallized
RGTi Graphite Application as the First Wall Material
in Globus-M Spherical Tokamak. (13 th International
Conference on Fusion Reactor Materials (ICFRM-13),
2007-12-10 to 2007-12-14, Nice).
Hamacher, T.: Die Kernfusion in der Energieversorgung der
Zukunft. (Deutsche Kälte-Klimatagung 2007, 2007-11-21 to
2007-11-23, Hannover).

Hamacher, T.: Role of Nuclear Fusion in a future energy
scenario. (IPP Summer University for Plasma Physics,
2007-09-24 to 2007-09-28, Greifswald).
Hamacher, T.: Safety and Environmental Aspects. (IPP
Summer University for Plasma Physics, 2007-09-24 to
2007-09-28, Greifswald).
Harhausen, J., C. Fuchs, A. Kallenbach, M. Wischmeier and
ASDEX Upgrade Team: Verteilung der Zuflussdichte von
Neutralteilchen in ASDEX Upgrade. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Harting, D., D. Reiter, H. Frerichs and Y. Feng: Model extensions
of the 3D edge plasma fluid Monte Carlo code EMC3.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Hatzky, R.: A new concept for efficiently parallelizing PIC
codes in plasma physics. (13 th ScicomP Conference (ScicomP13),
2007-07-16 to 2007-07-20, Garching).
Hauff, T. and F. Jenko: Redistribution of energetic particles by
background turbulence. (3 rd IAEA Technical Meeting on the
Theory of Plasma Instabilties, 2007-03-26 to 2007-03-28, York).
Heidinger, R., I. Danilov, A. Meier, A. Arnold, J. Flamm,
M. Thumm, F. Leuterer, J. Stober and D. Wagner: Low
power mm-wave transmission characteristics of a frequency
tuneable double disk CVD-diamond window. (32 nd International
Conference on Infrared and Millimeter Waves and
the 15 th International Conference on Terahertz Electronics
(IRMMW-THz 2007), 2007-09-02 to 2007-09-07, Cardiff).
Heilgeist, J., T. Soddemann and H. Richter: Algorithms for Job
and Resource Discovery for the Meta-Scheduler of the DEISA
Grid. (International Conference on Advanced Engineering
Computing and Applications in Sciences (ADVCOMP 2007),
2007-11-04 to 2007-11-09, Papeete, French Polynesia).
Hein, B., A. Cardella, D. Hermann, F. Leher and J. Segl:
Final manufacture of the outer vessel of the cryostat for
Wendelstein 7-X. (8 th International Symposium on Fusion
Nuclear Technology (ISFNT-8), 2007-09-30 to 2007-10-05,
Heidelberg).
Heinemann, B., M. Fröschle, R. Gutser, R. Nocentini, R. Riedl
and P. Angostinetti: Design of the Half-Size ITER Extraction
System for “ELISE”. (Coordinating Committee on Neutral
Beams (CCNB-Meeting), 2007-05-22 to 2007-05-24, Culham).
Heinemann, B., M. Fröschle, R. Gutser, R. Nocentini, R. Riedl,
P. Angostinetti and T. Jiang: Design Status of “ELISE” Testbed.
Lectures
157
(CCNB – Combined ITER Design and R&D Review and Coordination
Meeting, 2007-11-28 to 2007-12-01, Ahmedabad).
Heitmann, N.: Stochastic Model of the German Electricity
System. (78. Sitzung der GOR Arbeitsgruppe “Praxis der Mathematischen
Optimierung”, 2007-04-19 to 2007-04-20, Aachen).
Helander, P.: On rapid rotation in stellarators. (Joint Conference
of 17 th International Toki Conference on Physics of Flows and
Turbulence in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Henderson, M. A., G. Saibene, T. Bonicelli, R. Chavan, D. Farina,
D. Fasel, R. Heidinger, E. Poli, G. Ramponi, O. Sauter and
H. Zohm: Interface Issues associated with the ITER ECH
system. (4 th IAEA Technical Meeting on ECRH Physics and
Technology for ITER, 2007-06-06 to 2007-06-08, Vienna).
Hennig, C., T. Bluhm, P. Heimann, H. Kroiss, J. Maier,
H. Riemann and M. Zilker: Investigation of data losses when
using UDP communication. (6 th IAEA Technical Meeting on
Control, Data Acquisition and Remote Participation, 2007-06-04
to 2007-06-08, Inuyama).
Hennig, C., A. Werner, M. Marquardt, T. Bluhm, P. Heimann,
H. Kroiss, J. Maier, H. Riemann and M. Zilker: Continuous
data acquisition with on-line analysis for the Wendelstein7-X
magnetic diagnostics. (6 th IAEA Technical Meeting on Control,
Data Acquisition and Remote Participation, 2007-06-04 to
2007-06-08, Inuyama).
Hergenhahn, U.: Autoionisation von Molekülen und
Clustern in Elektron-Elektron Koinzidenzexperimenten.
(BESSY-Seminar, 2007-06-12, Berlin).
Hergenhahn, U.: Elektronenspektroskopie an freien Clustern.
(Seminar Physikalische Chemie, 2007-07-02, Freie Universität
Berlin).
Hergenhahn, U.: Interatomic/-molecular Coulombic Decay in
Clusters: An Introduction. (Nanoscience Seminar, 2007-08-30,
Universität Bergen).
Hergenhahn, U.: Photoelectron-Auger electron coincidence
spectroscopy. (Institute of Organic Chemistry and Biochemistry,
Academy of the Sciences, 2007-02-02, Prague).
Hergenhahn, U.: Schwach gebundene Cluster: Elektronenspektroskopie
und Autoionisation. (Clustertreffen 2007,
2007-09-23 to 2007-09-28, Berlin-Spandau).
Hergenhahn, U., S. Barth, V. Ulrich, S. Marburger, M. Lundwall,
G. Öhrwall and O. Björneholm: Effiziente Autoionisation

schwach gebundener Cluster durch Interatomaren Coulomb-
Zerfall (ICD). (DPG AMOP-Frühjahrstagung, 2007-03-19
to 2007-03-23, Düsseldorf).
Herrmann, A.: Power and particle exhaust measurements.
(International Workshop on Burning Plasma Diagnostics,
2007-09-24 to 2007-09-28, Varenna).
Herrmann, A., M. Balden and H. Bolt: Tungsten fibre reinforced
copper for high-temperature heat sink material for fusion
application. (16. Symposium: Verbundwerkstoffe und Werkstoffverbunde,
DGM, 2007-03-14 to 2007-03-16, Bremen).
Herrmann, A., M. Balden, A. Brendel and H. Bolt: Interfacial
characterisation of tungsten fibre reinforced copper
for high-temperature heat sink material for fusion application.
(European Congress and Exhibition on Advanced Materials
and Processes (EUROMAT 2007), 2007-09-10 to 2007-09-13,
Nürnberg).
Herrmann, A., K. Schmid, M. Balden and H. Bolt: Interfacial
optimization of tungsten fibre reinforced copper for
high-temperature heat sink material for fusion application.
(13 th International Conference on Fusion Reactor Materials
(ICFRM-13), 2007-12-10 to 2007-12-14, Nice).
Herrmann, J.: Challenges and Opportunities of an Interconnected
European and Russian Electricity Network. (9 th IAEE
European Energy Conference – Energy Markets and Sustainability
in a Larger Europe, 2007-06-10 to 2007-06-13,
Florence).
Hobirk, J., E. Joffrin and EFDA JET Contributors: Progress
in documentation of the hybrid scenario in JET. (49 th Annual
Meeting of the Division of Plasma Physics, 2007-11-12 to
2007-11-16, Orlando, FL).
Hölzl, M., S. Günter, Q. Yu and K. Lackner: Numerical modeling
of diffusive heat transport across magnetic islands and highly
stochastic layers. (Biennial Workshop “Stochasticity in Fusion
Plasmas” (SFP 2007), 2007-03-05 to 2007-03-07, Jülich).
Hopf, C., M. Schlüter and W. Jacob: Chemical sputtering of
carbon films by argon ions and molecular oxygen between
110 and 850 K. (Physique des Interactions Ioniques et
Moleculaires, 2007-06-25, Universite de Provence, Marseille).
Horton, L. D.: Physics Issues for DEMO. (Carolus Magnus
Summer School on Plasma and Fusion Energy Physics,
2007-09-03 to 2007-09-14, Bad Honnef).
Horton, L. D.: Reactor (Physics) Concepts. (Carolus Magnus
Summer School, 2007-09-03 to 2007-09-14, Bad Honnef).
Lectures
158
Hoshino, K., A. Hatayama, D. Coster, X. Bonnin, R. Schneider,
H. Kawashima, N. Asakura and Y. Suzuki: Benchmarking
kinetic and fluid neutral models with drift effects. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices
(PET 11), 2007-05-23 to 2007-05-25, Takayama-city).
Igitkhanov, Y., M. Kobyashi, S. Masuzaki, T. Morisaki,
B. J. Peterson, M. Shoji, H. Yamada, K. Kawahata, S. Sudo
and O. Motojima: Momentum removal from plasma flow in the
Helical island divertor. (11 th International Workshop on
Plasma Edge Theory in Fusion Devices (PET 11), 2007-05-23
to 2007-05-25, Takayama-city).
Igitkhanov, Y., A. Sagara, B. Peterson, S. Sudo and O. Motojima:
Impurity Control by small Pellet Injection at the Plasma
Edge of a Helical Device. (11 th International Workshop on
Plasma Edge Theory in Fusion Devices (PET 11), 2007-05-23
to 2007-05-25, Takayama-city).
Igochine, V.: RWM rotation experiments in RFX-mod. (RFXmod
Programme Workshop, 2007-12-13 to 2007-12-14, Padova).
Igochine, V., O. Dumbrajs, H. Zohm and A. Flaws: Stochastic
sawtooth reconnection in ASDEX Upgrade. (Biennial
Workshop “Stochasticity in Fusion Plasmas” (SFP 2007),
2007-03-05 to 2007-03-07, Jülich).
Jacob, W.: Materials Research at IPP. (Physique des Interactions
Ioniques et Moleculaires, 2007-06-26, Universite de
Provence, Marseille).
Jacob, W., C. Hopf and M. Schlüter: Chemical sputtering of
carbon films by argon ions and molecular oxygen between
110 and 850 K. (17 th International Vacuum Congress (IVC-17),
13 th International Conference on Surface Science (ICSS-13),
International Conference on Nano Science and Technology
(ICN+T 2007), 2007-07-02 to 2007-07-06, Stockholm).
Jacob, W., M. Schlüter, C. Hopf and T. Schwarz-Selinger:
Chemische Zerstäubung durch simultanen Beschuss von
Kohlenstoff mit Argonionen und molekularem Sauerstoff.
(14. Erfahrungsaustausch Oberflächentechnologie mit Plasmaund
Ionenstrahlprozessen, 2007-03-13 to 2007-03-15,
Mühlleithen).
Jakubowski, M., K.-H. Finken, M. Lehnen, O. Schmitz, B. Unterberg
and R. Wolf: Influence of Dynamic Ergodic Divertor on heat
and particle transport in TEXTOR. (Meeting of Polish
EURATOM Association, 2007-09-17 to 2007-09-21, Kudowa).
Jenko, F.: Theory and simulation on transport barriers.
(11 th IAEA TM on H-mode Physics and Transport Barriers,
2007-09-26 to 2007-09-28, Tsukuba).

Jenzsch, H., A. Cardella, J. Reich, W. Gardebrecht and
M. Bednarek: Final Design and Manufacture of the Cryolegs
to W7-X Superconducting Coil Magnet and Support System.
(8 th International Symposium on Fusion Nuclear Technology
(ISFNT-8), 2007-09-30 to 2007-10-05, Heidelberg).
Jüttner, B., S. Noack, A. Versteegh and G. Fußmann: Long-
Living Plasmoids from a Water Discharge at Atmospheric
Pressure. (28 th International Conference on Phenomena in
Ionized Gases (ICPIG), 2007-07-15 to 2007-07-20, Prague).
Kallenbach, A.: Die Eigenschaften des Randschichtplasma –
ein Schlüsselthema der kontrollierten Kernfusion. (Physikalisches
Kolloquium, 2007-04-23, Universität Augsburg).
Kallenbach, A.: Einführung in die Plasmaspektroskopie.
(SS 2007. Vorlesung, Universität Augsburg).
Kasparek, W., M. Petelin, D. Shchegolkov, V. Erckmann,
B. Plaum, A. Bruschi and ECRH Groups at IPP, FZK and IPF:
FADIS, a fast switch and combiner for high-power millimetre
wave beams. (4 th IAEA Technical Meeting on ECRH
Physics and Technology for ITER, 2007-06-06 to 2007-06-08,
Vienna).
Kaufmann, M.: Einführung in die Plasmaphysik und Fusionsforschung
I. (WS 2006/2007. Vorlesung, Universität Bayreuth).
Kaufmann, M.: Einführung in die Plasmaphysik und Fusionsforschung
II. (SS 2007. Vorlesung, Universität Bayreuth).
Kervalishvili, G. N., P. Kleiber, R. Schneider, B. D. Scott,
O. Grulke and T. Windisch: Intermittent turbulence in the
linear VINETA device. (11 th International Workshop on Plasma
Edge Theory in Fusion Devices (PET 11), 2007-05-23 to
2007-05-25, Takayama-city).
Kleiber, R., R. Hatzky and A. Mishchenko: Global gyrokinetic
simulations for stellarators. (Joint Conference of 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Kobayashi, M., Y. Feng, S. Masuzaki, T. Morisaki, S. Morita,
H. Yamada and LHD Experimental Group: Modelling of impurity
transport in ergodic layer of LHD. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices (PET 11),
2007-05-23 to 2007-05-25, Takayama-city).
Koch, F., S. Köppl and H. Bolt: Self Passivating W-based
Alloys as Plasma Facing Material. (13 th International Conference
on Fusion Reactor Materials (ICFRM-13), 2007-12-10
to 2007-12-14, Nice).
Lectures
159
König, R., R. Burhenn, J. Cantarini, K. Grosser, H. J. Hartfuß,
D. Hildebrandt, M. Hirsch, G. Kocsis, P. Kornejew, M. Laux,
E. Pasch, S. Recsei, J. Sachtleben, J. Sarközi, W. Schneider,
V. Szabó, H. Thomsen, A. Weller, A. Werner, R. Wolf, M. Y. Ye,
D. Zhang and S. Zoletnik: Diagnostic Developments for
Quasi-Continuous Operation of the W7-X Stellarator. (Inter
of Plasmas, 2007-10-16 to 2007-10-19, Greifswald).
König, R., J. Cantarini, K. Grosser, D. Hildebrandt, M. Hirsch,
G. Kocsis, P. Kornejew, M. Laux, E. Pasch, S. Recsei, V. Szabó,
H. Thomsen, A. Weller, A. Werner, R. Wolf, M. Ye and S. Zoletnik:
Diagnostic Developments for Quasi-Continuous Operation
of the Wendelstein 7-X Stellarator. (PLASMA 2007 – International
Conference on Research and Applications of Plasmas
combined with the 4 th German-Polish Conference on Plasma
Diagnostics for Fusion and Applications and the 6 th French-
Polish Seminar on Thermal Plasma in Space and Laboratory,
2007-10-16 to 2007-10-19, Greifswald).
Kolesnichenko, Y. I., V. V. Lutsenko, A. Weller, A. Werner,
Y. Yakovenko, J. Geiger and O. P. Fesenyuk: Modelling of lowfrequency
alfvénic activity in Wendelstein 7-AS. (34 th European
Physical Society Conference on Plasma Physics, 2007-07-02
to 2007-07-06, Warsaw).
Kolesnichenko, Y., V. V. Lutsenko, A. Weller, A. Werner, Y. Yakovenko
and J. Geiger: Low Frequency Alfvén Instabilities in Stellarators:
Peculiarities and the Use for Diagnostics. (10 th IAEA
Technical Meeting on Energetic Particles in Magnetic Confinement
Systems, 2007-10-08 to 2007-10-10, Kloster Seeon).
Kost, F. and C. Linsmeier: First results from beryllium on carbon.
(EFDA SEWG Meeting on Mixed Materials, 2007-07-09 to
2007-07-10, JET, Culham).
Kost, F. and C. Linsmeier: Reactions in the Ternary Be-C-W
System. (EFDA SEWG Meeting on Mixed Materials,
2007-07-09 to 2007-07-10, JET, Culham).
Kraus, W.: Long pulse operation of the IPP RF source. (Coordinating
Committee on Neutral Beams (CCNB-Meeting),
2007-05-22 to 2007-05-24, Culham).
Kraus, W. and NBI Team: Overview on the RF Source Development
Programme at IPP. (CCNB – Combined ITER Design
and R&D Review and Co-ordination Meeting, 2007-11-28
to 2007-12-01, Ahmedabad).
Kraus, W., R. Riedl, H.-D. Falter, U. Fantz, P. Franzen,
B. Heinemann, M. Fröschle, C. Martens, P. McNeely, M. Berger
and E. Speth: Long pulse large area beam extraction with an
RF driven H - /D - source. (12 th International Conference on
Ion Sources (ICIS 2007), 2007-08-26 to 2007-08-31, Jeju).

Krieger, K.: Plasma-Wall interaction basics for metallic materials.
(15 th European Fusion Physics Workshop, 2007-12-03
to 2007-12-05, Prague).
Krieger, K.: Plasma Wall Interaction and First Wall Materials.
(IPP Summer University for Plasma Physics, 2007-09-24 to
2007-09-28, Greifswald).
Krieger, K., I. Bizyukov, F. Kost, H. Lee, C. Linsmeier, M. Reinelt
and IPP PWI Group: Investigation of mixed material surface
processes and multi-species ion bombardment. (1 st IAEA
Research Co-ordination Meeting on Data for Surface Composition
Dynamics relevant to Erosion Processes, 2007-10-17
to 2007-10-19, Vienna).
Krieger, K., M. Stamp, S. Brezinsek, H. G. Esser, S. Jachmich,
A. Kreter, P. Mertens, V. Philipps, P. Sundelin and JET EFDA
Contributors: Be migration after Be evaporation in JET.
(JET Task Force E Migration Workshop, 2007-03-09, Culham).
Krieger, K., M. Stamp, S. Brezinsek, H. Esser, S. Jachmich,
A. Kreter, S. Menmuir, P. Mertens, V. Philipps, P. Sundelin and
EFDA JET Contributors: Evolution of Be migration after Be
evaporation in the JET tokamak. (34 th Conference on Plasma
Physics of the European Physical Society, 2007-07-02 to
2007-07-06, Warsaw).
Krychowiak, M., P. Mertens, B. Schweer, S. Brezinsek, R. König,
O. Schmitz, M. Brix, T. Klinger and U. Samm: LIF measurements
on an atomic helium beam in the edge of a fusion plasma –
possible derivation of the electron density. (PLASMA 2007 –
International Conference on Research and Applications of
Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Kus, A., E. Ascasibar, A. Dinklage, J. H. Harris, S. Okamura,
R. Preuss, F. Sano, U. Stroth, J. Talmadge and H. Yamada: Cluster
analysis of the International Stellarator Confinement Database.
(PLASMA 2007 – International Conference on Research
and Applications of Plasmas combined with the 4 th German-
Polish Conference on Plasma Diagnostics for Fusion and
Applications and the 6 th French-Polish Seminar on Thermal
Plasma in Space and Laboratory, 2007-10-16 to 2007-10-19,
Greifswald).
Kus, A., A. Krüger, A. Dinklage, T. Bluhm, C. G. Hanke, G. Kühner,
A. Werner, C. Hennig, J. Geiger, M. Lewerentz, Yu. Turkin and
W7-X Team: Unified Software Repositories for Wendelstein 7-X:
Workflow Elements for Fusion Software Development. (6 th IAEA
TM on Control, Data Acquisition, and Remote Participation
for Fusion Research, 2007-06-04 to 2007-06-08, Inuyama).
Lectures
160
Lang, P. T.: Pellet triggering as a tool to understand ELM
physics. (10 th ITPA MHD Topical Group Meeting, 2007-10-12,
Garching).
Lang, P. T.: Status of pellet pacing ELM control and prospects
for ITER. (Joint ITPA Meeting of Pedestal and Divertor &
SOL Topical Groups, 2007-05-07, Garching).
Lang, P. T., L. Fattorini, L. D. Horton, A. Kallenbach, K. Lackner,
W. Suttrop and ASDEX Upgrade Team: Pellet perturbations
for probing threshold conditions and investigating onset
dynamics of paced ELMs. (11 th IAEA TM on H-mode Physics
and Transport Barriers, 2007-09-26 to 2007-09-28, Tsukuba).
Lang, P. T., K. Lackner, L. Fattorini, A. Kallenbach, M. Maraschek,
J. Neuhauser, W. Suttrop and ASDEX Upgrade Team: Investigations
of pellet triggered MHD events in ASDEX Upgrade.
(10 th Workshop on the Electric Fields, Structures, and Relaxation
in Plasmas, 2007-07-08 to 2007-07-09, Warsaw).
Laqua, H., M. Otte, Y. Podoba, S. Marsen, WEGA-Team,
J. Preinhaelter, J. Urban and E. Holzhauer: Direct Measurement
of the Electron Bernstein Wave Heating and Current Drive
at the WEGA Stellarator. (49 th Annual Meeting of the Division
of Plasma Physics, 2007-11-12 to 2007-11-16, Orlando, FL).
Laqua, H. P.: Electron Bernstein Wave Heating and Current
Drive at the WEGA Stellarator. (19 th Joint Russian-German
Workshop on ECRH and Gyrotrons, 2007-07-18 to 2007-07-24,
Garching).
Laqua, H. P.: Electron Cyclotron Resonance Heating, Ion
Cyclotron Resonance Heating, Lower Hybrid Heating.
(International Summer School on Fusion Technologies,
2007-09-03 to 2007-09-14, Karlsruhe).
Laqua, H. P.: Intensive Mikrowellen im Plasma. (Kolloquium,
2007-05-03, Greifswald).
Laqua, H. P.: Intensive Mikrowellen im Plasma. (Kolloquium,
Institut für Hochleistungsimpuls- und Mikrowellentechnik,
2007-11-22, Forschungszentrum Karlsruhe).
Laqua, H. P.: The stellarator facility Wendelstein 7-X.
(International Summer School on Fusion Technologies,
2007-09-03 to 2007-09-14, Karlsruhe).
Laqua, H. P.: The transition into steady state W7-X operation
by ECCD and ECRH. (15 th European Fusion Physics
Workshop, 2007-12-03 to 2007-12-05, Prague).
Laqua, H. P., E. Holzhauer, S. Marsen, M. Otte, Y. Y. Podoba,
M. Schubert and G. B. Warr: Electron Cyclotron Wave Experi-

ments at the WEGA Stellarator. (34 th European Physical Society
Conference on Plasma Physics, 2007-07-02 to 2007-07-06,
Warsaw).
Lauber, P., S. Günter, H. L. Berk, M. Brüdgam, M. Garcia
Munoz and ASDEX Upgrade Team: Damping and drive of low
frequency modes in tokamak plasmas. (10 th IAEA Technical
Meeting on Energetic Particles, 2007-10-08 to 2007-10-10,
Kloster Seeon).
Lauber, P., S. Günter, S. da Graça, A. Könies, S. D. Pinches
and M. Brüdgam: Damping rates of global Alfvén waves in
tokamaks. (3 rd IAEA Technical Meeting on the Theory of
Plasma Instabilties, 2007-03-26 to 2007-03-28, York).
Lauber, P., S. Günter, S. da Graça, A. Könies, S. D. Pinches
and M. Brüdgam: Damping rates of global Alfvén waves in
tokamaks. (3 rd IAEA Technical Meeting on the Theory of
Plasma Instabilties, 2007-03-26 to 2007-03-28, York).
Lechte, C., E. Holzhauer, G. Conway, W. Kasparek and U. Stroth:
Simulation von Doppler-Reflektometrie in turbulenten Plasmen
mit Finite Difference Time Domain Codes. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Lederer, H.: DEISA: on the way towards an integrated European
HPC ecosystem. (13th ScicomP Conference (ScicomP13),
2007-07-16 to 2007-07-20, Garching).
Lederer, H.: Erste Erfahrungen mit dem weltweit ersten
BlueGene/P System. (ZKI-Tagung, 2007-10-25, GWDG
Göttingen).
Lederer, H.: Garching BlueGene/P: First Application Performance
Results. (BlueGene Consortium Meeting, 2007-11-13,
Reno, NV).
Lederer, H., R. Tisma, R. Hatzky, A. Bottino and F. Jenko:
Application Enabling in DEISA: Hyperscaling of Turbulence
Codes Supporting ITER. (Parallel Computing (ParCo),
2007-09-03 to 2007-09-07, Jülich).
Lederer, H., R. Tisma, R. Hatzky, A. Bottino and F. Jenko:
Application Enabling in DEISA: Petascaling of Plasma
Turbulence Codes. (Parallel Computing (ParCo), 2007-09-03
to 2007-09-07, Jülich).
Lederer, H., R. Tisma, R. Hatzky, A. Bottino and F. Jenko: Towards
Petascale Computing in Support of ITER. (13 th ScicomP
Conference (ScicomP13), 2007-07-16 to 2007-07-20, Garching).
Leuterer, F., H. Schütz, J. Stober and D. Wagner: Overview
of the ASDEX Upgrade ECRH system performance in 1998
Lectures
161
to 2007. (19 th Russian-German STC Workshop on ECRH and
Gyrotrons, 2007-07-23, Garching).
Levchuk, D.: Permeation barriers for hydrogen applications.
(9 th International Workshop on Plasma-Based Ion Implantation
& Deposition (PBIID-07), 2007-09-02 to 2007-09-06,
Leipzig).
Levchuk, D., K. Ertl, H. Maier and H. Bolt: Radiation damage
effect on the performance of tritium permeation barriers.
(8 th International Symposium on Fusion Nuclear Technology
(ISFNT-8), 2007-09-30 to 2007-10-05, Heidelberg).
Linke, J., T. Hirai, P. Mertens, B. Schweer and H. Altmann:
Status of the ITER-like JET divertor. (ITER Divertor Meeting,
2007-11-07 to 2007-11-09, Barcelona).
Linsmeier, C.: The European Integrated Project on Materials for
Extreme Environments. (European Congress and Exhibition
on Advanced Materials and Processes (EUROMAT 2007),
2007-09-10 to 2007-09-13, Nürnberg).
Linsmeier, C.: Ion Scattering Spectroscopy. (Fritz-Haber-
Institut, 2007-01-12, Berlin).
Linsmeier, C.: Materials issues in fusion and relation to other
applications. (Jahrestagung Kerntechnik 2007, 2007-05-24
to 2007-05-24, Karlsruhe).
Linsmeier, C.: New materials for extreme environments in
fusion applications. (Schwerpunktseminar Schwerpunkt
Ionen- und Plasmaphysik/Angwandte Physik, 2007-05-14
to 2007-05-14, Universität Innsbruck).
Linsmeier, C.: Oberflächenreaktionen auf Beryllium aus der
Perspektive der Kernfusion. (Humboldt-Universität, 2007-01-11,
Berlin).
Linsmeier, C.: Overview on the ExtreMat project. (2 nd KMM-
NoE Integration Conference, 2007-10-24 to 2007-10-25,
Vienna).
Linsmeier, C.: Surface Chemistry of Fusion First Wall
Materials. (Kolloquium Physikalische Chemie, 2007-07-19,
Universität München).
Linsmeier, C., H. Bolt, M. Balden, A. Brendel, K. Ertl,
F. Koch, F. Kost, D. Levchuk, H. Maier, J. Roth, K. Schmid
and A. Wiltner: Materialien in der Kernfusion: Plasmabelastung
und chemisches Verhalten. (16. Diskussionstagung
Anorganisch-Technische Chemie, 2007-02-21 to 2007-02-22,
Dechema, Frankfurt).

Linsmeier, C., H. Bolt, M. Balden, A. Brendel, F. Koch, D. Levchuk,
H. Maier, K. Ertl, J. Roth, A. Wiltner, F. Kost and K. Schmid:
Neue Materialien für den Einsatz unter extremen Anforderungen
in der Kernfusion. (ISC-Seminar, 2007-02-02,
Fraunhofer-Institut für Silicatforschung, Würzburg).
Loarer, T., J. Roth, S. Brezinsek, A. Kirschner, M. Mayer, R. Neu,
V. Philipps, V. Rohde, M. Rubel and E. Tsitrone: Tritium
Intentory in ITER: Laboratory data and extrapolation from
tokamaks. (6 th Meeting of Contact Persons of the EU-PWI
Task Force, 2007-10-29 to 2007-10-31, Madrid).
Lopez-Galilea, I., N. Ordas, C. Garcia-Rosales and S. Lindig:
Improvement of Thermal Shock Resistance of Isotropic Graphite
by Ti-doping. (13 th International Conference on Fusion Reactor
Materials (ICRFM-13), 2007-12-10 to 2007-12-14, Nice).
Lunt, T. and G. Fußmann: Messungen mit Laserinduzierter
Fluoreszenz in der Nähe eines absorbierenden Targets.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Lutsenko, V. V., Y. Kolesnichenko, A. Weller, A. Werner,
H. Wobig and A. V. Tykhyy: Effect of the Radial Electric Field
on the Confinement of Fast Ions in Optimized Stellarators.
(10 th IAEA Technical Meeting on Energetic Particles in
Magnetic Confinement Systems, 2007-10-08 to 2007-10-10,
Kloster Seeon).
Mahdizadeh, N., F. Greiner, T. Happel, A. Kendl, M. Ramisch,
B. Scott and U. Stroth: Dreidimensionale Dynamik von Driftwellenturbulenz.
(DPG AMOP-Frühjahrstagung, 2007-03-19
to 2007-03-23, Düsseldorf).
Maisberger, F., U. Fantz and NNBI-Team: Messung zur Plasmahomogenität
an HF-Quellen zur Erzeugung negativer Ionen.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Manini, A., K. Behler, L. Giannone, F. Leuterer, M. Maraschek,
F. Monaco, G. Neu, G. Raupp, A. Sips, J. Stober, W. Suttrop,
W. Treutterer, D. Wagner, H. Zohm, S. Cirant, F. Gandini,
G. D’Antona, H. Bindslev, F. Leipold and F. Meo: Implementation
of a feedback system for MHD control with ECRH using
real time fast steerable mirrors. (19 th Russian-German STC
Workshop on ECRH and Gyrotrons, 2007-07-23, Garching).
Manini, A., G. Gantenbein, M. Maraschek, N. Hicks, F. Leuterer,
R. Neu, J. Stober, W. Suttrop, D. Wagner, H. Zohm and
ASDEX Upgrade Team: Plasma stability enhancement using
EC-RH/CD in ASDEX Upgrade. (4 th IAEA Technical Meeting
on ECRH Physics and Technology for ITER, 2007-06-06 to
2007-06-08, Vienna).
Lectures
162
Manini, A., M. Maraschek, G. Gantenbein, Q. Yu, H. Zohm,
S. Günter, F. Leuterer and ASDEX Upgrade Team: Increasing
NTM stabilization efficiency using modulated ECCD in ASDEX
Upgrade. (17 th Topical Conference on Radio Frequency
Power in Plasmas, 2007-05-07 to 2007-05-09, Clearwater, FL).
Mantsinen, M. J., R. Bilato, Vl. Bobkov, L.-G. Eriksson,
H.-U. Fahrbach, M. Garcia-Muñoz, J.-M. Noterdaeme,
W. Schneider and ASDEX Upgrade Team: Analysis of ICRFaccelerated
ions in ASDEX Upgrade. (17 th Topical Conference
on Radio Frequency Power in Plasmas, 2007-05-07 to
2007-05-09, Clearwater, FL).
Mantsinen, M. J. and JET-EFDA Contributors: Modification
of sawtooth oscillations with ICRF waves in the JET
tokamak. (17 th Topical Conference on Radio Frequency Power
in Plasmas, 2007-05-07 to 2007-05-09, Clearwater, FL).
Manz, P., V. Naulin, R. Ramisch, B. Scott and U. Stroth: Experimentelle
Untersuchung des nichtlinearen Energietransfers
in zweidimensionaler Plasmaturbulenz. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Marsen, S., M. Otte, M. Schubert and F. Wagner: Zur Struktur
turbulenter Fluktuationen am Stellarator WEGA. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Marsen, S., M. Otte and F. Wagner: Structure of Turbulence
in the WEGA Stellarator. (7 th International Workshop on
Electrical Probes in Magnetized Plasmas, 2007-07-22 to
2007-07-25, Prague).
Marushchenko, N. B., C. D. Beidler, V. Erckmann, H. Maaßberg
and Yu. Turkin: ECCD scenarios for different configurations
of the W7-X Stellarator. (Joint Conference of the 17 th International
Toki Conference on Physics of Flows and Turbulence
in Plasmas (ITC) and 16 th International Stellarator/Heliotron
Workshop, 2007-10-15 to 2007-10-19, Ceratopia Toki, Gifu).
Marushchenko, N. B., V. Erckmann, H. P. Laqua, H. Maaßberg
and Yu. Turkin: Analysis of ECCD scenarios for different
configurations of the W7-X Stellarator. (19 th Joint Russian-
German Workshop on ECRH and Gyrotrons, 2007-07-19 to
2007-07-24, Garching).
Marushchenko, N. B., V. Erckmann, H. P. Laqua, H. Maaßberg
and Y. Turkin: Calculations of ECCD for W7-X & ITER.
(Theory Meeting Sellin, 2007-11-19 to 2007-11-23, Sellin).
Marushchenko, N. B., H. Maaßberg and Y. Turkin: Electron
Cyclotron Current Drive Predictions for ITER: comparison of
different models. (4 th IAEA Technical Meeting on ECRH Physics
and Technology for ITER, 2007-06-06 to 2007-06-08, Vienna).

Marushchenko, N. B., H. Maaßberg and Yu. Turkin: Electron
Cyclotron Current Drive Preditions for ITER: comparsion of
the different models. (19 th Joint Russian-German Workshop
on ECRH and Gyrotrons, 2007-07-18 to 2007-07-24, Garching).
Masuzaki, S., M. Kobayashi, Y. Feng, T. Morisaki, T. Watanabe,
N. Ohyabu and LHD Experimental Group: Study of edge
plasma transport in LHD. (11 th International Workshop on
Plasma Edge Theory in Fusion Devices (PET 11), 2007-05-23
to 2007-05-25, Takayama-city).
Matyash, K., R. Schneider, R. Sydora and F. Tacogna: Application
of Complex Particle Kinetics to collisionless sheath.
(11 th International Workshop on Plasma Edge Theory in
Fusion Devices (PET 11), 2007-05-23 to 2007-05-25,
Takayama-city).
Mayer, M.: FT 3.25: Erosion/Deposition in the JET divertor.
(Special TFE meeting on material erosion, migration and
fuel retention in JET, 2007-03-09 to 2007-03-09, Culham).
Mayer, M.: RESOLNRA: A new program for optimizing the
achievable depth resolution in ion beam analysis methods.
(18 th International Conference on Ion Beam Analysis,
2007-09-23 to 2007-09-28, Hyderabad, India).
Mayer, M., V. Rohde, J. Chen, X. Gong, J. Likonen, S. Lindig,
G. Ramos, E. Vainonen-Ahlgren and ASDEX Upgrade Team:
Carbon Erosion and Transport in ASDEX Upgrade. (9 th ITPA
Meeting on SOL/divertor physics, 2007-05-07 to 2007-05-10,
Garching).
Mayer, M., V. Rohde, J. Chen, X. Gong, J. Likonen, S. Lindig,
G. Ramos, E. Vainonen-Ahlgren and ASDEX-Upgrade Team:
Erosion of carbon and tungsten in the outer divertor of
ASDEX-Upgrade. (2 nd German-Finnish Workshop on Material
Migration in Fusion Devices: Measurements and Modelling,
2007-02-26 to 2007-02-27, Tervaniemi).
Mayer, M., V. Rohde, J. Likonen, S. Lindig, G. Ramos, E. Vainonen-
Ahlgren and ASDEX Upgrade Team: W marker erosion in
ASDEX Upgrade. (Special Expert Working Group meeting
on High-Z Plasma Facing Components, 2007-05-10 to
2007-05-11, Garching).
Mayer, M., V. Rohde, G. Ramos, E. Vainonen-Ahlgren, J. Likonen,
A. Herrmann and ASDEX Upgrade Team: Deuterium Inventory
in ASDEX Upgrade. (9 th ITPA Meeting on SOL/divertor
physics, 2007-05-07 to 2007-05-10, Garching).
Meyer-Spasche, R.: Frauen in Mathematik und Physik. (Herbstuniversität
für Schülerinnen, 2007-10-29 to 2007-10-30,
Technische Universität München).
Lectures
163
Meyer-Spasche, R.: Introduction to Functional Analysis.
(WS 2006/2007. Vorlesung, Technische Universität München).
Meyer-Spasche, R.: Mathematische Probleme in Fluiddynamik
und Plasmaphysik. (SS 2007. Vorlesung, Technische
Universität München).
Michel, G., H. Braune, V. Erckmann, H. Laqua, F. Noke, F. Purps,
M. Dammertz, M. Thumm, C. Lechte and O. Dumbrais: Dual
frequency operation of the W7-X gyrotron. (19 th Joint Russian-
German Workshop on ECRH and Gyrotrons, 2007-07-18 to
2007-07-24, Karlsruhe/Stuttgart/Garching).
Michel, G., F. Noke and P. Uhren: Integrated long-pulse control
of gyrotrons. (19 th Joint Russian-German Workshop on
ECRH and Gyrotrons, 2007-07-18 to 2007-07-24, Karlsruhe/
Stuttgart/Garching).
Mishchenko, A., A. Könies, P. Helander, Y. Turkin and
R. Kleiber: Collisionless damping of zonal flow in 3D geometry.
(Theory Meeting Sellin, 2007-11-19 to 2007-11-23,
Sellin).
Missal, B., A. Cardella, M. Schrader, T. Koppe and P. Friedrich:
Mechanical Experiments about Pendulum Support of Vacuum
Vessel W7-X. (8 th International Symposium on Fusion Nuclear
Technology (ISFNT-8), 2007-09-30 to 2007-10-05, Heidelberg).
Moro, A., W. A. Bongers, A. Bruschi, M. F. Graswinckel, E. Poli,
D. M. S. Ronden and A. G. A. Verhoeven: Beam characteristics
including general astigmatism effects in the Remote Steering
ITER ECRH Upper Launcher. (4 th IAEA Technical Meeting
on ECRH Physics and Technology for ITER, 2007-06-06 to
2007-06-08, Vienna).
Mueck, A., A. Flaws, A. Gude and V. Igochine: Recent Development
of the Soft X-Ray Diagnostic System in ASDEX
Upgrade. (DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Müller, H. W.: Basic Plasma Physics. (IPP Summer University
for Plasma Physics, 2007-09-24 to 2007-09-28, Greifswald).
Müller, W.-C. and M. Momeni: Monoscaling and Lévy laws
in turbulence. (10 th MHD Days, 2007-11-26 to 2007-11-29,
Garching).
Neu, R.: Experimental results. (IPP Summer University on
Plasma Physics, 2007-09-24 to 2007-09-28, Greifswald).
Neu, R.: Fourth Report of the SEWG on Hig-Z PFCs. (6 th
Meeting of Contact Persons of the EU-PWI Task Force,
2007-10-29 to 2007-10-31, Madrid).

Neu, R.: Initial operation of ASDEX Upgrade with 100 %
tungsten PFCs. (9 th ITPA Meeting on Divertor and SOL
Physics, 2007-05-10 to 2007-05-11, IPP Garching).
Neu, R.: Kernfusion – eine Option für morgen? (Veranstaltung
Studium Generale, 2007-06-12, Universität Tübingen).
Neu, R.: Kernfusion – eine zukünftige Energiequelle? (Veranstaltung
der Akademie für Lehrerfortbildung und Personalführung,
2007-09-05, Dillingen).
Neu, R.: Operation with metallic wall: Feedback from AUG
and FTU. (EFPW Meeting, 2007-12-03 to 2007-12-05, Prague).
Neu, R.: Operation with tungsten plasma facing components
in ASDEX Upgrade. (CEA Seminar, 2007-09-21, Cadarache).
Neu, R.: Plasmaphysik und Fusionsforschung I. (WS 2006/
2007, SS 2007. Vorlesung, Universität Tübingen).
Neu, R.: Plasmaphysik und Fusionsforschung II. (SS 2007.
Vorlesung, Universität Tübingen).
Neu, R.: Wolfram – eine Option für ITER? (Plasmakolloquium
des IPF, 2007-04-07, Universität Stuttgart).
Neu, R. and ASDEX Upgrade Team: Plasma operation with
high-Z environment. (17 th International Vacuum Congress
(IVC-17), 13 th International Conference on Surface Science
(ICSS-13), International Conference on Nano Science and
Technology (ICN+T 2007), 6 th Nordic Conference on
Surface Science (NCSS-6), 22 nd Nordic Semiconductor
Meeting (NSM-22), 4 th Swedish Meeting on Vacuum and
Materials Science (SVM-4), 2007-06-07 to 2007-06-06,
Stockholm).
Neu, R. and ASDEX Upgrade Team: The Tungsten programme
at ASDEX Upgrade. (ADAS Workshop, 2007-10-10 to
2007-10-13, Schloss Ringberg, Tegernsee).
Neu, R., V. Bobkov, R. Dux, T. Eich, H. Greuner, O. Gruber,
A. Herrmann, L. Horton, A. Kallenbach, M. Kaufmann, P. Lang,
C. F. Maggi, H. W. Müller, R. Pugno, T. Pütterich, V. Rohde,
W. Schustereder, A. C. C. Sips, J. Stober, W. Suttrop,
M. Wischmeier, H. Zohm and ASDEX Upgrade Team:
Plasma operation in a divertor tokamak with all tungsten
plasma facing components. (49 th Annual Meeting of the
Division of Plasma Physics, 2007-11-12 to 2007-11-16,
Orlando, FL).
Neu, R., R. Dux, A. Kallenbach and ASDEX Upgrade Team:
Plasma operation with high-Z-environment. (Meeting, University
of Stockholm, 2007-07-08 to 2007-07-09, Stockholm).
Lectures
164
Neu, R., T. Pütterich, R. Dux and ASDEX Upgrade Team:
Spectroscopic Diagnostic of Tungsten in Fusion Plasmas.
(Physics at EBIT and Advanced Research Light Sources
(PEARL07), 2007-03-08 to 2007-03-14, Shanghai).
Noack, S., A. Versteegh, B. Jüttner and G. Fußmann:
Analysis of Long-Living Plasmoids at Atmospheric Pressure.
(PLASMA 2007 – International Conference on Research
and Applications of Plasmas combined with the 4 th German-
Polish Conference on Plasma Diagnostics for Fusion and
Applications and the 6 th French-Polish Seminar on Thermal
Plasma in Space and Laboratory, 2007-10-16 to 2007-10-19,
Greifswald).
Noack, S., A. Versteegh, B. Jüttner and G. Fußmann:
Spektroskopische Untersuchung von langlebigen Plasmoiden.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Nold, B., M. Ramisch, V. Rohde, ASDEX Upgrade Team and
U. Stroth: Vergleich dimensional ähnlicher Turbulenz in TJ-K
und ASDEX Upgrade. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Noterdaeme, J.-M.: EnTicE: European network on Training
ion cyclotron Engineers. (ICRF Meetings 2007 (TFH/JET-
ITER/EnTicE/EFDA Coordination Task Meeting), 2007-04-16
to 2007-04-20, Schloss Ringberg, Tegernsee).
Noterdaeme, J.-M.: ICRF Research and Development Needs.
(EFDA Meeting: Heating and Current Drive Research and
Developments, 2007-07-03, Warsaw).
Noterdaeme, J.-M.: ITER – ICRF and EnTicE. (Kolloquium,
Institute of Plasma Physics, 2007-09-20, Prague).
Noterdaeme, J.-M.: Kernreactortheorie. (WS 2006/2007.
Vorlesung, Universiteit Gent).
Noterdaeme, J.-M.: Nuclear Reactor Theory and Experiments.
(SS 2007. Vorlesung – Interuniversity Program Master, Nuclear
Engineering, SCK/CEN (Studiencentrum voor Kernenergie/
Centre pour Energie Nucleaire), Mol).
Noterdaeme, J.-M.: Wave heating for fusion plasmas. (Erasmus
Mundus – Fusion EP, 2007-07-19 to 2007-07-23, Zollernblick).
Omar, B., A. Wierling, S. Günter and G. Poeke: Spectral line
shapes in dense plasmas. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Otte, M.: Plasmatechnik: Fusionsplasmen. (WS 2006/2007.
Vorlesungen, Fachhochschule Stralsund).

Otte, M., D. Andruczyk, A. Komarov, A. Kozachek, L. Krupnik,
H. P. Laqua, O. Lischtschenko, S. Marsen, Y. Y. Podoba,
M. Schubert, F. Wagner, G. B. Warr and A. Zhezhera: Experimental
results from the WEGA stellarator. (34 th European
Physical Society Conference on Plasma Physics, 2007-07-02
to 2007-07-06, Warsaw).
Otte, M., D. Andruczyk, H. P. Laqua, O. Lischtschenko, S. Marsen,
Y. Podoba, J. Schacht, F. Wagner, G. Warr and A. Werner:
The WEGA experiment: results and prospect. (PLASMA
2007 – International Conference on Research and Applications
of Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications
and the 6 th French-Polish Seminar on Thermal Plasma in
Space and Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Pfannmöller, J., O. Grulke, T. Klinger and K. Sauer: Experimentelle
Untersuchungen nicht-linearer Phänomene von
Whistlerwellen. (DPG AMOP-Frühjahrstagung, 2007-03-19
to 2007-03-23, Düsseldorf).
Podoba, Y., M. Otte, F. Wagner, M. Schubert, I. Bondarenko,
A. Chmyga, G. Deshko, A. Komarov, A. Kozachok, L. Krupnik,
S. Khrebtov, A. Zhezhera, A. Melnikov and S. Perfilov: First
HIBP results on the WEGA Stellarator. (PLASMA 2007 –
International Conference on Research and Applications of
Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Podoba, Y., M. Schubert and A. Zhezhera: First Results of
Heavy Ion Beam Probing at WEGA. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Pokol, G., G. Papp, G. Por, S. Zoletnik, A. Weller and W7-AS Team:
Experimental Study and Simulation of W7-AS Transient MHD
Mode. (PLASMA 2007 – International Conference on Research
and Applications of Plasmas combined with the 4 th German-
Polish Conference on Plasma Diagnostics for Fusion and Applications
and the 6 th French-Polish Seminar on Thermal Plasma in
Space and Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Poli, E.: Introduction to kinetic plasma theory. (IPP Summer
University for Plasma Physics, 2007-09-24 to 2007-09-28,
Greifswald).
Poli, E., W. A. Bongers, A. Bruschi, D. Farina, M. F. Graswinckel,
M. A. Henderson, A. Moro, G. Ramponi, G. Saibene,
A. G. A. Verhoeven and H. Zohm: Performance Evaluation of the
Remote-Steering Option for the ITER EC Upper Launcher.
(4 th IAEA Technical Meeting on ECRH Physics and Technology
for ITER, 2007-06-06 to 2007-06-08, Vienna).
Lectures
165
Poli, E., A. Peeters, A. Bergmann and A. Bottino: Dynamics
of magnetic islands in tokamak. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Preinhaelter, J., J. Urban, H. P. Laqua, L. Vahala and G. Vahala:
Simulations of EBW heating in WEGA. (17 th Topical Conference
on Radio Frequency Power in Plasmas, 2007-05-07 to
2007-05-09, Clearwater, FL).
Preuss, R. and U. von Toussaint: Comparison of numerical
methods for evidence calculation. (27 th International Workshop
on Bayesian Inference and Maximum Entropy Methods
in Science and Engineering (MaxEnt 2007), 2007-07-08 to
2007-07-13, Saratoga Springs, NY).
Preuss, R. and U. von Toussaint: Numerical integration
methods for model comparison. (27 th International Workshop
on Bayesian Inference and Maximum Entropy Methods in
Science and Engineering (MaxEnt 2007), 2007-07-08 to
2007-07-13, Saratoga Springs, NY).
Rademann, D.: Leak Testing at Wendelstein 7-X during
Assembly. (Symposium on Vacuum based Science and Technology,
2007-09-05 to 2007-09-07, Greifswald).
Rahbarnia, K., E. Holzhauer, F. Greiner, A. Kendl, N. Mahdizadeh,
M. Ramisch, B. Scott and U. Stroth: Elektromagnetische Turbulenz
in TJ-K und ihre Abhängigkeit vom Plasma-β. (DPG
AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Rampp, M.: MIGenAS: Max-Planck Integrated Gene Analysis
System. (CASIMIR First Networking Meeting, 2007-10-03
to 2007-10-06, Corfu).
Rampp, M.: Computational aspects of large-scale analysis of
metagenomics data. (Workshop SEQU07 – The Challenges in
High-Throughput DNA-Sequencing, 2007-04-30, Neuherberg).
Rampp, M.: An Infrastructure for Computational Biology
Applications. (Joint MPG-CNRS Workshop on “Systems
Biology”, 2007-09-24 to 2007-09-26, Berlin).
Ramponi, G., D. Farina, M.A. Henderson, E. Poli, O. Sauter,
G. Saibene, H. Zohm, C. Zucca and H. Takahashi: Physics
analysis of the ITER ECW system for an optimized performance.
(4 th IAEA Technical Meeting on ECRH Physics and
Technology for ITER, 2007-06-06 to 2007-06-08, Vienna).
Reich, J., A. Cardella, U. Nielsen, R. Krause, R. Kairys, H. Jenzsch,
M. Bednarek, G. Sobisch and B. Voslamber: Manufacture of
Inter-Coil-Support-Elements of the W7-X Magnet System.
(22 nd Symposium on Fusion Engineering, 2007-06-17 to
2007-06-21, Albuquerque, NM).

Reinelt, M. and C. Linsmeier: Deuterium Retention in Ocovered
and Pure Beryllium. (EFDA SEWG Meeting on
Mixed Materials, 2007-07-09 to 2007-07-10, JET, Culham).
Reiter, D., H. Frerichs, D. Harting, Y. Feng and O. Schmitz:
3D edge transport studies with EMC3-EIRENE for the Dynamic
Ergodic Divertor (DED) at TEXTOR. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices
(PET 11), 2007-05-23 to 2007-05-25, Takayama-city).
Ribeiro, T.: Edge turbulence simulations: self consistent MHD
equilibrium and the X-point singularity. (12 th European
Fusion Theory Conference, 2007-09-23 to 2007-09-27,
Madrid).
Rohde, V.: Dust production by arc erosion. (Workshop on Dust
in ITER – Technology Issues (Dust in Tokamak), Satellite
Meeting of the 13 th International Conference on Fusion Reactor
Materials (ICFRM-13), 2007-12-14 to 2007-12-15, Nice).
Rohde, V.: Comparison of the 13 puff and long-term measurements.
(2 nd German-Finnish Workshop on Material Migration
in Fusion Devices, 2007-02-26 to 2007-02-27, Tervaniemi).
Rohde, V., M. Balden, P. Sharpe, G. Antar and ASDEX Upgrade
Team: Dust investigations at ASDEX Upgrade. (1 st Workshop
on the “Dust in Fusion Plasmas”. Satellite Meeting of
the 34 th EPS Conference on Plasma Physics, 2007-07-08 to
2007-07-10, Warsaw).
Roth, J.: Choice of wall materials and compatibility of plasma
operation. (2 nd EFDA Workshop, 2007-10-08 to 2007-10-09,
Cadarache).
Roth, J.: ITER Design Review and the EU PWI TF. (PMK
Strategieklausur, 2007-06-18, Garching).
Roth, J.: Migration pattern of D into CFC. (ITPA SOL/Divertor
Meeting, 2007-05-07 to 2007-05-10, Garching).
Roth, J.: PWI and Edge Physics. (1 st EFDA Workshop,
2007-07-17 to 2007-07-19, Garching).
Roth, J. and E. Tsitrone: The EU-PWI Task Force: recent
achievements and midterm program. (EU PWI TF, STAC
Meeting, 2007-02-08 to 2007-02-09, Brussels).
Roth, J., E. Tsitrone and A. Loarte: The EU Plasma Wall
Interaction Task Force: recent achievements and midterm
program. (Association Day ÖAW, 2007-06-19, Innsbruck).
Roth, J., E. Tsitrone and A. Loarte: The EU Plasma Wall
Interaction Task Force: recent achievements and midterm
Lectures
166
program. (Meeting of the Association Euratom-IPPLM
Council, 2007-03-20, Warsaw).
Roth, J., E. Tsitrone and A. Loarte: The EU-PWI Task
Force: Work-Programme 2008. (EU PWI TF STAC Meeting,
2007-05-24, Brussels).
Roth, J., E. Tsitrone and A. Loarte: Plasma-Wall Interaction:
A complex combination of surface processes critical for
thermo-nuclear fusion. (Berliner Seminar über Plasmaphysik,
2007-03-14, Humboldt-Universität Berlin).
Roth, J., E. Tsitrone and A. Loarte: Plasma-Wall Interaction:
A complex combination of surface processes critical for
thermo-nuclear fusion. (17 th International Vacuum Congress,
2007-07-02 to 2007-07-06, Stockholm).
Roth, J., E. Tsitrone, A. Loarte, G. F. Counsell and R. P. Doerner:
Tritium inventory in ITER plasma-facing materials and
tritium removal procedures. (13 th International Conference
on Fusion Reactor Materials (ICFRM-13), 2007-12-10 to
2007-12-14, Nice).
Rozhansky, V., E. Kaveeva, S. Voskoboynikova and D. Coster:
Modelling of the radial electric field in the ASDEX Upgrade
Ohmic shots. (11 th International Workshop on Plasma Edge
Theory in Fusion Devices (PET 11), 2007-05-23 to 2007-05-25,
Takayama-city).
Ruset, C., E. Grigore, H. Maier and R. Neu: Combined
Magnetron Sputtering and Ion Implantation – a High Energy
Ion Assisted Deposition Method for Producing Nanostructurated
Coatings. (Materials Science & Technology 2007
Conference, 2007-09-16 to 2007-09-20, Detroit, MI).
Ryter, F., J. C. Fuchs, W. Schneider, A. C. C. Sips, A. Stäbler,
J. Stober and ASDEX Upgrade Team: H-mode confinement
properties close to the power threshold in ASDEX Upgrade.
(11 th IAEA TM on H-mode Physics and Transport Barriers,
2007-09-26 to 2007-09-28, Tsukuba).
Ryter, F., J. C. Fuchs, W. Schneider, A. C. C. Sips, J. Stober
and ASDEX Upgrade Team: Status of the ASDEX Upgrade
data in the ITPA confinement data base. (12 th ITPA Confinement
Database and Modelling Workshop, 2007-05-07 to
2007-05-10, Lausanne).
Rzesnicki, T., B. Piosczyk, J. Flamm, G. Gantenbein, J. Jin,
M. Thumm and G. Michel: The quasi-optical RF output system
for the 170 GHz, 2 MW coaxial cavity gyrotron. (19 th Joint
Russian-German Workshop on ECRH and Gyrotrons,
2007-07-18 to 2007-07-24, Karlsruhe/Stuttgart/Garching).

Sangines, R., D. Andruczyk, R. N. Tarrant, M. M. Bilek and
D. R. Mc Kenzie: Characterization of a filtered pulsed catholic
vacuum wave plasma source: plasma transport analysis.
(PLASMA 2007 – International Conference on Research and
Applications of Plasmas combined with the 4 th German-Polish
Conference on Plasma Diagnostics for Fusion and Applications
and the 6 th French-Polish Seminar on Thermal Plasma in
Space and Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Sardei, F., A. Brooks, Y. Feng, F. Herrnegger, T. Kaiser,
J. Kißlinger, R. Maingi, D. Monticello and M.C. Zarnstorff:
EMC3-EIRENE implementation on NCSX and first applications.
(Joint Conference of 17 th International Toki Conference
on Physics of Flows and Turbulence in Plasmas and
16 th International Stellarator/Heliotron Workshop, 2007-10-15
to 2007-10-19, Ceratopia Toki, Gifu).
Sárközi, J., K. Grosser, G. Kocsis, R. König, U. Neuner,
A. Molnár, G. Petravich, G. Por, G. Porempovics, S. Recsei,
V. Szabó, A. Szappanos and S. Zoletnik: Video Diagnostic
for W7-X Stellarator. (International Conference Plasma
2007 on Research and Application of Plasmas, 2007-10-16
to 2007-10-19, Greifswald).
Schacht, J., H. Laqua, A. Spring, I. Müller, S. Pingel and
A. Wölk: Stellarator WEGA as a test-bed for the Wendelstein 7-X
control system concepts. (6 th IAEA Technical Meeting on
Control, Data Acquisition, and Remote Participation for
Fusion Research, 2007-06-04 to 2007-06-08, Inuyama).
Schacht, J., H. Laqua, A. Spring, I. Müller, S. Pingel, A. Wölk
and G. Kühner: Standardized communication in the control
system of the experiment Wendelstein 7-X. (15 th IEEE Real
Time Conference, 2007-04-28 to 2007-05-04, Batavia).
Schacht, J., S. Pingel and A. Wölk: Die Konzeption der Sicherheitssteuerung
für das Fusionsexperiment Wendelstein 7-X.
(12. Symposium Maritime Elektrotechnik, Elektronik und
Informationstechnologie, 2007-10-08 to 2007-10-10, Rostock).
Schmitz, O., M. W. Jakubowski, T. E. Evans, M. J. Schaffer,
W. P. West, M. E. Fenstermacher, M. Groth, C. Lasnier,
I. Joseph, R. Moyer, B. Unterberg and H. Frerichs: Divertor
heat and particle fluxes during ELM control experiments.
(49 th Annual APS Division of Plasma Physics Meeting,
2007-11-12 to 2007-11-16, Orlando, FL).
Schmuck, S., A. Dinklage, R. Fischer, J. P. Knauer, B. Kurzan,
H.-D. Murmann and E. Pasch: Design and calibration of
Thomson scattering polychromator for Wendelstein 7-X.
(PLASMA 2007 – International Conference on Research and
Applications of Plasmas combined with the 4 th German-Polish
Conference on Plasma Diagnostics for Fusion and Applica-
Lectures
167
tions and the 6 th French-Polish Seminar on Thermal Plasma in
Space and Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Schmuck, S., A. Dinklage, R. Fischer, J. P. Knauer, B. Kurzan,
H.-D. Murmann and E. Pasch: Optimierung eines Detektionssystems
für die Thomson-Streuung. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Schustereder, W., N. Endstrasser, B. Rasul, F. Zappa, V. Grill,
P. Scheier and T. Märk: Quantification of the sticking coefficient
of hydrocarbons on fusion relevant carbon and tungsten
surfaces. (28 th International Conference on Phenomena
in Ionized Gases (ICPIG), 2007-07-15 to 2007-07-20, Prague).
Schwarz, B., P. Worbs and C. Eisenmenger-Sittner: Applications
of a High Temperature Sessile Drop Device. (17 th International
Vacuum Congress (IVC-17), 13 th International
Conference on Surface Science (ICSS-13), International Conference
on Nano Science and Technology (ICN+T 2007),
6 th Nordic Conference on Surface Science (NCSS-6),
22 nd Nordic Semiconductor Meeting (NSM-22), 4 th Swedish
Meeting on Vacuum and Materials Science (SVM-4), 2007-07-02
to 2007-07-06, Stockholm).
Schwarz-Selinger, T.: Quantitative Mass Spectrometry of
Reactive Plasmas – Sensitivity Studies with Bayesian Data
Analysis. (Symposium on Vacuum Based Science and Technology,
2007-09-05 to 2007-09-07, Greifswald).
Schwarz-Selinger, T. and W. Jacob: Stickstoffbeimischung
in die Plasmarandschicht – eine Lösung für die Redepositionsproblematik
in Fusionsexperimenten. (Arbeitsgruppenseminar,
Lehrstuhl für experimentelle Plasmaphysik,
2007-10-09, Humboldt-Universität Berlin).
Schwarz-Selinger, T., W. Jacob and C. Hopf: Stickstoffbeimischung
in Kohlenwasserstoffplasmen – eine Lösung für die
Redepositionsproblematik in Fusionsexperimenten? (14. Erfahrungsaustausch
Oberflächentechnologie mit Plasma- und
Ionenstrahlprozessen, 2007-03-13 to 2007-03-15, Mühlleithen).
Schweinzer, J.: Atomic collision processes in plasmas of
ASDEX Upgrade, JET and ITER. (Atomphysik Seminar,
2007-11-14, Darmstadt).
Schweinzer, J.: Atomic collision processes in plasmas of
ASDEX Upgrade, JET and ITER. (20 th International Symposium
on Ion-Atom Collisions, 2007-08-02 to 2007-08-04,
Agios Nikolaos).
Schweinzer, J.: The lithium beam modelling database and its
extension to sodium. (ADAS Workshop, 2007-10-12, Schloss
Ringberg, Tegernsee).

Schweinzer, J.: Status of ASDEX Upgrade. (IEA Large
Tokamak & Poloidal Divertor Workshop on Implementation
of ITPA Coordinated Research Recommendations, 2007-11-29,
Culham).
Schweinzer, J. and E. Wolfrum: Grundlagen des Kernfusionsreaktors.
(SS 2007. Vorlesung, Technische Universität Wien).
Scott, B.: Self Consistent Nonlinear Burst Phenomena in
Tokamak Edge Turbulence. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Seidel, R., C. Biedermann, R. Radtke and T. Pütterich: Experimentelle
und theoretische Bestimmung der Wellenlängen
von Emissionslinien im Röntgenbereich hochgeladener
Wolframionen. (DPG AMOP-Frühjahrstagung, 2007-03-19
to 2007-03-23, Düsseldorf).
Shimizu, S., T. Shimizu, W. Jacob, H. Thomas, N. Sato and
G. E. Morfill: Microcrystalline Diamond Growth on Seed
Particles and Thermophoretic Effect on Levitated Fine
Diamond Particles in an RF Plasma Sheath. (18 th European
Conference on Diamond, Diamond-Like Materials, Carbon
Nanotubes, and Nitrides, 2007-09-09 to 2007-09-14, Berlin).
Shimozuma, T., S. Kubo, H. Igami, Y. Yoshimura, T. Notake,
N. B. Marushchenko, Yu. Turkin, T. Mutoh and LHD Experimental
Group: Efficient heating at the 3 rd harmonic Electron
cyclotron resonance in Large Helical Device. (Joint Conference
of the 17 th International Toki Conference on Physics of
Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to 2007-10-19,
Ceratopia Toki, Gifu).
Simon-Weidner, J.: The Shrunk Finite Element (SFE) Method:
Simulation of Crack Propagation in 3-D. (NAFEMS World
Congress, 2007-05-22 to 2007-05-25, Vancouver).
Stäbler, A. and AUG-Team: The Role of the Different
Heating Systems in Optimising ASDEX Upgrade Discharges.
(EFDA Meeting: Heating and Current Drive Research and
Developments, 2007-07-03, Warsaw).
Stark, A., W. Fox, J. Egedal, O. Grulke and T. Klinger: Observation
of localized ion heating during driven collisionless
magnetic reconnection. (The 9 th International Workshop on
the Interrelationship between Plasma Experiments in Laboratory
and Space (IPELS), 2007-08-05 to 2007-08-10, Cairns).
Stark, A., O. Grulke and T. Klinger: Experimentelle Untersuchungen
zu nichtlinear angeregten alfvénischen Wellen in
VINETA. (DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Lectures
168
Stark, A., O. Grulke and T. Klinger: Nonlinear excitation of
Alfvénic waves by helicon modulation. (The 9 th International
Workshop on the Interrelationship between Plasma
Experiments in Laboratory and Space (IPELS), 2007-08-05
to 2007-08-10, Cairns).
Starke, P., C. Adelhelm, M. Balden and U. Fantz: Chemical
Erosion of Doped Carbon Layers in Deuterium Low Pressure
FR Plasmas. (European Congress and Exhibition on Advanced
Materials and Processes (EUROMAT 2007), 2007-09-10 to
2007-09-13, Nürnberg).
Starke, P., C. Adelhelm, M. Balden, U. Fantz, A. Centeno and
C. Blanco: Erosionsausbeuten dotierter Kohlenstoffmaterialien
in Deuterium-Niedertemperaturplasmen. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Starke, P., S. Christ-Koch, S. K. Karkari, C. Gaman, U. Fantz
and A. R. Ellingboe: Performance of a Langmuir probe and
a hairpin resonance probe in inductively coupled low pressure
plasmas. (28 th International Conference on Phenomena in
Ionized Gases (ICPIG), 2007-07-15 to 2007-07-20, Prague).
Stober, J., A. Manini, M. Maraschek, F. Meo, R. Neu, D. Wagner,
H. Zohm and ASDEX Upgrade Team: ASDEX Upgrade
results with the upgraded ECRH system. (19 th Joint Russian-
German Meeting on ECRH and Gyrotrons, 2007-07-23,
Garching).
Stober, J., A. C. C. Sips, C. Angioni, C. B. Forest, O. Gruber,
J. Hobirk, L. D. Horton, C. F. Maggi, M. Maraschek, P. Martin,
P. J. McCarthy, V. Mertens, Y.-S. Na, M. Reich, A. Stäbler,
G. Tardini, H. Zohm and ASDEX Upgrade Team: The role of
the current profile in the improved H-mode scenario in
ASDEX Upgrade. (49 th Annual Meeting of the Division of
Plasma Physics, 2007-11-12 to 2007-11-16, Orlando, FL).
Strumberger, E., S. Günter, E. Schwarz, C. Tichmann and
ASDEX Upgrade Team: Fast Particle Losses Due to NTMS
and Magnetic Field Ripple. (49 th Annual Meeting of the
Division of Plasma Physics, 2007-11-12 to 2007-11-16,
Orlando, FL).
Strumberger, E., P. Merkel, M. Sempf and S. Günter: Fully
3D RWM and Feedback Stabilization Studies for ITER and
AUG. (49 th Annual Meeting of the Division of Plasma Physics,
2007-11-12 to 2007-11-16, Orlando, FL).
Subba, F., X. Bonnin, D. Coster, A. Kukushkin, A. Loarte,
D. Reiter and R. Zanino: 2D Fluid Modeling of far SOL
Divertor Plasma Including the First Wall. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices (PET 11),
2007-05-23 to 2007-05-25, Takayama-city).

Suttrop, W.: Tokamak equilibrium, transport and stability.
(IPP Summer University on Plasma Physics, 2007-09-24 to
2007-09-28, Greifswald).
Suttrop, W., T. Bertoncelli, P. Brunsell, T. Eich, E. Gaio, O. Gruber,
F. Gnesotto, S. Günter, P. Merkel, M. Rott, T. Vierle, S. Schweizer,
U. Seidel, M. Sempf, B. Streibl, E. Strumberger, V. Toigo, H. Zohm
and ASDEX Upgrade Team: Design of in-vessel saddle coils
at ASDEX. (Biennial Workshop “Stochasticity in Fusion
Plasmas” (SFP 2007), 2007-03-05 to 2007-03-07, Jülich).
Suzuki, A., T. Chikada, B. A. Pint, D. Levchuk, T. Muroga and
T. Terai: Fabrication and properties of Fe-erbia double layer
coatings on V alloy for Li/V blanket application. (22 nd Symposium
on Fusion Engineering (SOFE 07), 2007-06-18 to
2007-06-22, Albuquerque, NM).
Suzuki, A., B. Pint, M. Li, D. Levchuk, F. Koch, T. Muroga and
T. Terai: Compatibility of MHD coating candidate materials
with liquid lithium under neutron irradiation. (13 th International
Conference on Fusion Reactor Materials (ICFRM-13),
2007-12-10 to 2007-12-14, Nice).
Suzuki, Y., H. Kawashima, D. P. Coster, S. Sakurai, K. Shimizu
and T. Takizuka: Simulation Study of Radiative Cooling in
the Divertor on JT-60 Super Advanced (JT-60SA). (11 th International
Workshop on Plasma Edge Theory in Fusion Devices
(PET 11), 2007-05-23 to 2007-05-25, Takayama-city).
Sydorenko, N., A. Grulke, A. Stark and T. Klinger: Measurements
of the negative ion concentration in argon-oxygen
discharges using photodetachment. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Szepesi, T., S. Kalvin, G. Kocsis, P. T. Lang and ASDEX Upgrade
Team: Investigations of the ELM triggering mechanism:
HFS and LFS pellet injections. (10 th Workshop on the Electric
Fields, Structures, and Relaxation in Plasmas, 2007-07-08 to
2007-07-09, Warsaw).
Taccogna, F., R. Schneider, S. Longo and M. Capitelli: Plasma-
Neutral Interaction in Kinetic Models for the Divertor Region.
(11 th International Workshop on Plasma Edge Theory in Fusion
Devices (PET 11), 2007-05-23 to 2007-05-25, Takayama-city).
Thomsen, H., P. Carvalho, U. v. Toussaint, S. Gori, S. Mohr and
A. Weller: The Steady-State Challenge for the X-Ray Tomography
System on Wendelstein 7-X stellarator. (PLASMA 2007 –
International Conference on Research and Applications of
Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Lectures
169
Thumm, M., G. Dammertz, G. Gantenbein, S. Illy, W. Leonhardt,
G. Neffe, B. Piosczyk, M. Schmid, H. Braune, V. Erckmann,
H. P. Laqua, G. Michel, M. Weißgerber, P. Brand, W. Kasparek
and C. Lechte: 10 MW, 140 GHz, CW gyrotron and optical transmission
system for millimeter wave heating of plasmas in
the stellarator W7-X. (1 st Shenzhen International Conference
on Advanced Science and Technology – THz Radiation
Science and Technology, 2007-11-18 to 2007-11-23, Shenzhen).
Thumm, M., G. Dammertz, G. Gantenbein, S. Illy, W. Leonhardt,
G. Neffe, B. Piosczyk, M. Schmid, H. Braune, V. Erckmann,
H. P. Laqua, G. Michel, M. Weißgerber, P. Brand, W. Kasparek
and C. Lechte: 10 MW, 140 GHz, CW millimeter wave heating
system for nuclear fusion plasma heating. (41 st IMPI Annual
Microwave Symposium, 2007-08-01 to 2007-08-03, Vancouver).
Thumm, M., G. Dammertz, G. Gantenbein, S. Illy, W. Leonhardt,
G. Neffe, B. Piosczyk, M. Schmid, H. Braune, V. Erckmann,
H. Laqua, G. Michel, M. Weißgerber, P. Brand, W. Kasparek
and C. Lechte: Progress on the 10 MW, 140 GHz ECH
System for the stellarator W7-X. (IEEE 2007 Pulsed Power
and Plasma Physics Conference, 2007-06-17 to 2007-06-22,
Albuquerque, NM).
Tomarchio, V. and K. Riße: The Manufacturing of the W7-X
Superconducting Magnet System. (International Youth Conference
on Energetics, 2007-05-31 to 2007-06-02, Budapest).
Tsitrone, E., A. Loarte and J. Roth: Modelling activities of
EU-PWI Task Force. (Annual Meeting of the Task Force
ITM, 2007-09-19 to 2007-09-21, Garching).
Tskhakaya, D., S. Kuhn, Y. Tomita, K. Matyash, R. Schneider
and F. Taccogna: Self-consistent simulations of the plasmawall
transition layer. (11 th International Workshop on Plasma
Edge Theory in Fusion Devices (PET 11), 2007-05-23 to
2007-05-25, Takayama-city).
Tskhakaya, D., F. Subba, X. Bonnin, D. Coster, W. Fundamenski,
R. A. Pitts and JET EFDA Contributors: On kinetic effects
during the parallel transport in the SOL. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices (PET 11),
2007-05-23 to 2007-05-25, Takayama-city).
Turkin, Y., C. D. Beidler, V. Erckmann, H. P. Laqua, H. Maaßberg,
N. B. Marushchenko and W7-X Team: ECRH and transport
simulation for W7-X. (34 th European Physical Society Conference
on Plasma Physics, 2007-07-02 to 2007-07-06, Warsaw).
Turkin, Y., C. D. Beidler, V. Erckmann, H. P. Laqua, H. Maaßberg,
N. B. Marushchenko and W7-X Team: ECRH and transport
simulation for W7-X. (19 th Joint Russian-German Workshop
on ECRH and Gyrotrons, 2007-07-18 to 2007-07-24, Garching).

Turkin, Y., C. D. Beidler, V. Erckmann, H. P. Laqua, H. Maaßberg,
N. B. Marushchenko and W7-X Team: Electron cyclotron
heating of plasma with density above 10 20 m -3 in W7-X. (Joint
Conference of the 17 th International Toki Conference on
Physics of Flows and Turbulence in Plasmas and 16 th International
Stellarator/Heliotron Workshop, 2007-10-15 to
2007-10-19, Ceratopia Toki, Gifu).
Turkin, Y., C. D. Beidler and H. Maaßberg: Predictive transport
code: status and plans. (3 rd Coordinated Working Group
Meeting (CWGM), 2007-10-23 to 2007-10-24, Toki).
Ullrich, S., O. Grulke and T. Klinger: Experimentelle Untersuchungen
zur Wechselwirkung von Drift- und Alfvénwellen.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Ulrich, V., S. Barth, S. Joshi, T. Lischke and U. Hergenhahn:
Energieaufgelöste koinzidente Messung von Photo- und
Augerelektron nach Innerschalenionisation bei CO, CF 4 und O 2 .
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Vermare, L., C. Angioni, A. Bottino, A. G. Peeters and ASDEX
Upgrade Team: β dependence of micro-instabilities using linear
gyrokinetic simulations. (11 th IAEA TM on H-mode Physics
and Transport Barriers, 2007-09-26 to 2007-09-28, Tsukuba).
Vermare, L., C. C. Petty, G. R. McKee, F. Ryter, J. R. Ferron,
R. J. Gröbner, A. W. Hyatt, A. W. Leonard, T. C. Luce, ASDEX
Upgrade Team and DIII-D Team: Comparison of the β dependence
of micro-instabilities using linear gyrokinetic simulations.
(11 th IAEA TM on H-mode Physics and Transport
Barriers, 2007-09-26 to 2007-09-28, Tsukuba).
Versteegh, A., S. Noack, B. Jüttner and G. Fußmann: Analysis
of long living plasmoid at atmospheric pressure. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Von Toussaint, U.: Integrated Data Analysis. (Institutskolloquium,
Institute for Plasma Research, 2007-02-06, Bhat, Gandhinagar).
Von Toussaint, U.: Introduction to Bayesian Probability
Theory: A Tutorial. (Theory-Group Institute for Plasma
Research, 2007-02-22, Bhat, Gandhinagar).
Von Toussaint, U.: IPP: Experiments and Research. (Institutskolloquium,
Institute for Plasma Research, 2007-02-20,
Bhat, Gandhinagar).
Von Toussaint, U.: Towards sustainable fusion power.
(California Institute of Technology, 2007-06-28 to 2007-06-28,
Pasadena, CA).
Lectures
170
Von Toussaint, U. and S. Gori: Deconvolution using Thin-
Plate Splines. (27 th International Workshop on Bayesian
Inference and Maximum Entropy Methods in Science and
Engineering (MaxEnt 2007), 2007-07-08 to 2007-07-13,
Saratoga Springs, NY).
Von Toussaint, U. and S. Gori: Echtzeitauswertung von ASDEX
Bolometriedaten. (CODAC Seminar, 2007-01-23 to 2007-01-25,
Internationales Begegnungszentrum (IBZ), Garching).
Von Toussaint, U. and P. N. Maya: Molecular Dynamics
Modeling of Chemical Erosion of Carbon Films. (13 th International
Conference on Fusion Reactor Materials (ICFRM-13),
2007-12-10 to 2007-12-14, Nice).
Wagner, D., F. Leuterer, A. Manini, F. Monaco, M. Münich,
H. Schütz, J. Stober, H. Zohm, T. Franke, M. Thumm,
R. Heidinger, I. Danilov, G. Gantenbein, J. Flamm, W. Kasparek,
A. G. Litvak, L. G. Popov, V. O. Nichiporenko, V. E. Myasnikov,
G. G. Denisov, E. M. Tai, E. A. Solyanova and S. A. Malygin:
Commissioning of the second two-frequency gyrotron in the
new ECRH system of ASDEX Upgrade, IRMMW-THz 2007.
(32 nd International Conference on Infrared and Millimeter
Waves and the 15 th International Conference on Terahertz
Electronics (IRMMW-THz 2007), 2007-09-02 to 2007-09-07,
Cardiff).
Wagner, D., F. Leuterer, J. Stober, A. Manini, F. Monaco,
M. Münich, H. Schütz, H. Zohm, T. Franke, M. Thumm,
R. Heidinger, I. Danilov, G. Gantenbein, J. Flamm, W. Kasparek,
A. G. Litvak, L. G. Popov, V. O. Nichiporenko, V. E. Myasnikov,
G. G. Denisov, E. M. Tai, E. A. Solyanova and S. A. Malygin:
Present status of the new multi-frequency ECRH system for
ASDEX Upgrade. (IEEE 2007 Pulsed Power and Plasma Physics
Conference, 2007-06-17 to 2007-06-22, Albuquerque, NM).
Wagner, D., F. Leuterer, J. Stober, A. Manini, F. Monaco,
M. Münich, H. Schütz, H. Zohm, T. Franke, M. Thumm,
R. Heidinger, I. Danilov, G. Gantenbein, J. Flamm, W. Kasparek,
A. G. Litvak, L. G. Popov, V. O. Nichiporenko, V. E. Myasnikov,
G. G. Denisov, E. M. Tai, E. A. Solyanova and S. A. Malygin:
Progress with the new mulit-frequency ECRH system for
ASDEX Upgrade. (19 th Joint Russian-German Meeting on
ECRH and Gyrotrons, 2007-07-23, Garching).
Wagner, D., F. Leuterer, J. Stober, A. Manini, F. Monaco,
M. Muenich, H. Schütz, H. Zohm, T. Franke, M. Thumm,
R. Heidinger, I. Danilov, G. Gantenbein, J. Flamm, W. Kasparek,
A. G. Litvak, L. G. Popov, V. O. Nichiporenko, V. E. Myasnikov,
G. G. Denisov, E. M. Tai, E. A. Solyanova and S. A. Malygin:
Status of the new multi-frequency ECRH system for ASDEX
Upgrade. (4 th IAEA Meeting on ECRH Physics and Technology
for ITER, 2007-06-06 to 2007-06-08, Vienna).

Wagner, F.: Energiepolitik für Deutschland aus der Sicht der
Forschung. (Verein deutscher Studenten, 2007-12-04,
Greifswald).
Wagner, F.: Energy and Physics in Europe. (Energy Symposium,
2007-08-31, Helsinki).
Wagner, F.: The EU Stellarator Programme. (NCSX Review,
2007-09-14 to 2007-09-19, Princeton, NJ).
Wagner, F.: Fusion and the physics behind magnetic confinement.
(Physikalisches Kolloquium am Institut für Theoretische
Physik, 2007-05-24, Bremen).
Wagner, F.: Fusion Research in Europe. (EPS Energy Meeting,
2007-01-15 to 2007-01-17, Cork).
Wagner, F.: H-mode Transition Physics. (Southwestern
Institute of Physics (SWIP), 2007-03-30 to 2007-04-04,
Chengdu).
Wagner, F.: H-modes on W7-AS. (KFKI-Research Institute
for Particle and Nuclear Physics, 2007-02-06, Budapest).
Wagner, F.: Introduction to High Temperature Plasma Physics
Part II. (WS 2006/2007. SS 2007. Vorlesung, Universität
Greifswald).
Wagner, F.: Opening Session – Welcome Speech. (9 th EUPEN
General Forum EGF 2007, 2007-09-06 to 2007-09-08,
Sant Feliu de Guíxols).
Wagner, F.: Opening Session – Welcome Speech. (GIREP
EPEC Conference, 2007-08-26 to 2007-08-31, Opatija).
Wagner, F.: Opening Session – Welcome Speech. (From Quantum
to Cosmos, 2007-06-10 to 2007-06-13, Bremen).
Wagner, F.: Physics of and Achievements with the H-mode.
(ITER Reactor Physics Summer School, 2007-07-16 to
2007-07-20, Aix-en-Provence).
Wagner, F.: Physics in Electricity Production. (IPSEC VI
(XXXIX Congress of Polish Physicists), 2007-09-09 to
2007-09-14, Stettin).
Wagner, F.: Die Rolle von Energietechnologien: Was würde
Klimaschutz heute kosten? (Rostocker Wirtschaftsgespräche
– Quo vadis Bundesrepublik?, 2007-09-25, Rostock).
Wagner, F.: The status of fusion research. (5 th International
Student Conference of the Balkan Physical Union (ISCBPU-5),
2007-08-21 to 2007-08-24, Bodrum).
Lectures
171
Wagner, F.: A quarter-century of H-mode studies. (24 th European
Conference on Controlled Fusion and Plasma Physics,
2007-07-02 to 2007-07-06, Warschau).
Wagner, F.: Stand und Zukunft der Fusionsforschung mit
magnetischem Einschluss. (Physikalisches Kolloquium der
Technische Universität Dresden, 2007-06-05, Dresden).
Wagner, F.: The Wendelstein Stellarator Line. (Southwestern
Institute of Physics (SWIP), 2007-03-30 to 2007-04-04,
Chengdu).
Waldmann, O.: Transport in Magnetized Plasma: Research
for the Development of Fusion Devices. (Pöringer Gespräche:
An interdisciplinary dialogue on complex problem solving,
2007-05, Landsberg).
Waldmann, O. and G. Fußmann: Influence of the Langmuir
probe shaft on measuring plasma parameters. (7 th International
Workshop on Electric Probes in Magnetised Plasmas
(IWEP 2007), 2007-07-22 to 2007-07-25, Prague).
Waldmann, O., G. Fußmann and I. Vizgalov: Massenspektrometermessungen
in magnetisierten Plasmen. (DPG AMOP-
Frühjahrstagung, 2007-03-19 to 2007-03-23, Düsseldorf).
Wanner, M. and T. Rummel: Study of extended steady state
Operation of the Magnet System of Wendelstein 7-X. (5 th
Technical Meeting on Steady State Operation of Magnetic
Fusion Devices, 2007-05-14 to 2007-05-17, Daejeon).
Wegener, L.: Wendelstein 7-X at the transition to assembly.
(Jahrestagung Kerntechnik 2007, 2007-05-22 to 2007-05-24,
Karlsruhe).
Weller, A., K. Y. Watanabe, S. Sakakibara, A. Dinklage,
H. Funaba, J. Geiger, J. H. Harris, R. Preuss, Y. Suzuki, A. Werner,
H. Yamada, W7-AS Team and LHD Team: Extensions of the
International Stellarator Database by High-b Data from W7-AS
and LHD. (Joint Converence of 17 th International Toki Conference
on Physics of Flows and Turbulence in Plasmas and
16 th International Stellarator/Heliotron Workshop, 2007-10-15
to 2007-10-19, Ceratopia Toki, Gifu).
Werner, A.: Einschluss überthermischer Ionen in Fusionsplasmen.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to
2007-03-23, Düsseldorf).
Windisch, T., O. Grulke, G. N. Kervalishvili, R. Schneider,
R. Kleiber and T. Klinger: Formation and propagation of
turbulent structures in drift-wave turbulence. (11 th International
Workshop on Plasma Edge Theory in Fusion Devices
(PET 11), 2007-05-23 to 2007-05-25, Takayama-city).

Wischmeier, M., A. V. Chankin and D. Coster: Possibilites
and Limitations of the SOLPS code package. (2 nd German
Finish Workshop, 2007-02-26 to 2007-02-27, Tarveniemi).
Wischmeier, M., D. Coster, X. Bonnin, A. V. Chankin, M. Groth,
R. Pugno, J. Harhausen, A. Kallenbach, E. Wolfrum and
H. W. Müller: Issues in simulating divertor detachment of ohmic
discharges: examples from ASDEX Upgrade using SOLPS5.0.
(Plasma Boundary Group Meeting, 2007-09-26, San Diego, CA).
Wischmeier, M., D. Coster, A. Chankin, A. Kallenbach,
H. W. Müller, M. Tsalas and ASDEX Upgrade Team: Simulating
the role of intrinsic carbon impurities in the divertor
detachment of ASDEX Upgrade. (11 th International Workshop
on Plasma Edge Theory in Fusion Devices (PET 11),
2007-05-23 to 2007-05-25, Takayama-city).
Wischmeier, M., A. Kallenbach, A. V. Chankin, D. P. Coster,
R. Dux, J. Harhausen, H. W. Müller, ASDEX Upgrade Team,
M. Groth and X. Bonnin: The influence of high field side
recycling and impurity sources on divertor detachment in
simulations of ohmic discharges of the ASDEX Upgrade
and DIII-D tokamaks. (49 th Annual Meeting of the Division
of Plasma Physics, 2007-11-12 to 2007-11-16, Orlando, FL).
Wolf, R. and W7-X Team: A Stellarator Reactor based on the
Optimization Criteria of Wendelstein 7-X. (8 th International
Symposium on Fusion Nuclear Technology, 2007-10-01 to
2007-10-05, Heidelberg).
Wolfrum, E.: The current status of the lithium beam diagnostic
at ASDEX Upgrade. (ADAS Workshop, 2007-10-10
to 2007-10-13, Schloss Ringberg, Tegernsee).
Wolfrum, E.: Kernfusion. (Abschlussveranstaltung für das EU
Projekt “Pallas Athene”, 2007-10-11 to 2007-10-12, Berlin).
Wolfrum, E. and S. Schweinzer: Grundlagen des Fusionsreaktors.
(SS 2207. Vorlesung, Universität Wien).
Worbs, P., B. Schwarz, H. Maier and H. Bolt: TiC coatings
as wetting promoter for optimizing carbon/copper brazed
joints in high heat flux components. (European Congress
and Exhibition on Advanced Materials and Processes
(EUROMAT 2007), 2007-09-10 to 2007-09-13, Nürnberg).
Woskov, P. P., H. Bindslev, S. B. Korsholm, F. Leipold, F. Meo,
P. K. Michelsen, S. Michelsen, S. K. Nielsen, E. L. Tsakadse,
E. Westerhof, H. Oosterbeek, J. Hoekzema, F. Leuterer and
D. Wagner: Gyrotron collective Thomson scattering of fast
ions in TEXTOR and ASDEX Upgrade. (IEEE 2007 Pulsed
Power and Plasma Physics Conference, 2007-06-17 to
2007-06-22, Albuquerque, NM).
Lectures
172
Wünderlich, D. and NNBI Team: Rechnungen zum Einfluss
von Bias und Magnetfeldern auf die Randschicht in einer
Quelle für negative Wasserstoffionen. (DPG AMOP-Frühjahrstagung,
2007-03-19 to 2007-03-23, Düsseldorf).
Xanthopoulos, P., F. Jenko, F. Merz and T. Görler: Gyrokinetic
Simulations of the ITG mode for the Optimized
Stellarator Wendelstein 7-X. (12 th European Fusion Theory
Conference, 2007-09-23 to 2007-09-27, Madrid).
Xanthopoulos, P., F. Jenko, F. Merz and T. Görler: Gyrokinetic
Simulations of Microinstabilities for the Stellarator
Wendelstein 7-X. (3 rd IAEA Technical Meeting on the Theory
of Plasma Instabilties, 2007-03-26 to 2007-03-28, York).
Xanthopoulos, P., F. Jenko, F. Merz, T. Görler and D. Mikkelsen:
Gyrokinetic Turbulence Simulations for Stellarators. (49 th Annual
APS Division of Plasma Physics Meeting, 2007-11-12 to
2007-11-16, Orlando, FL).
Yakovenko, Y., A. Weller, A. Werner, S. Zegenhagen, O. P. Fesenyuk
and Y. Kolesnichenko: Effect of the Three-Dimensionality
of the Magnetic Geometry on Alfvén Instabilities in Stellarators.
(10 th IAEA Technical Meeting on Energetic Particles in
Magnetic Confinement Systems, 2007-10-08 to 2007-10-10,
Kloster Seeon).
Yao, Z., A. Suzuki, D. Levchuk, T. Chikada, T. Tanaka, T. Muroga
and T. Terai: Hydrogen Permeation through Steel coated
with Erbium Oxide by Sol-gel Method. (13 th International
Conference on Fusion Reactor Materials (ICFRM-13),
2007-12-10 to 2007-12-14, Nice).
Yao, Z., A. Suzuki, D. Levchuk and T. Terai: Hydrogen permeation
through steel coated with silicon carbide. (8 th International
Conference on Tritium Science and Technology
(ICTST8), 2007-09-16 to 2007-09-21, Rochester, NY).
You, J. H.: Application of a fibre-reinforced copper matrix
composite cooling tube to a water cooled mono-block divertor
component: A design study. (13 th International Conference
on Fusion Reactor Materials (ICFRM-13), 2007-12-10 to
2007-12-14, Nice).
You, J. H.: Engineering application of shakedown analysis
to a composite structures reinforced with fibrous metal
matrix composites. (Werkstoffmechanisches Kolloqium,
2007-11-08 to 2007-11-09, RWTH Aachen).
You, J. H.: Integrated modelling approaches on multi-scales
for failure analysis of a composite structure with fibre-reinforced
metal matrix composite. (GKSS Workshop “Material
Models”, 2007-06-11 to 2007-06-12, Hamburg).

You, J. H.: Integrated modelling approaches on multi-scales
for failure analysis of a composite structure with fibre-reinforced
metal matrix composite. (MPA Institut, 2007-06-21,
Universität Stuttgart).
You, J. H.: Integrated modelling approaches on multi-scales
for failure analysis of a composite structure with fibre-reinforced
metal matrix composite. (Werkstoffmechanisches
Kolloquium, 2007-10-05, RWTH Aachen).
You, J. H.: Schichtmechanik. (WS 2006/2007. Vorlesung
“Dünne Schichten”, Technische Universität München).
Yu, Q., S. Günter, Y. Kikuchi and K. H. Finken: Nonlinear
calculation of the penetration threshold of the error field.
(Biennial Workshop “Stochasticity in Fusion Plasmas”
(SFP 2007), 2007-03-05 to 2007-03-07, Jülich).
Yu, Q., M. Hölzl, S. Günter and K. Lackner: Theoretical Studies
on Heat Diffusion across Magnetic Island and Local Stochastic
Magnetic Field. (Biennial Workshop “Stochasticity in
Fusion Plasmas” (SFP 2007), 2007-03-05 to 2007-03-07, Jülich).
Zacharias, T., U. Fantz and NNBI-Team: Ortsaufgelöste H α
Dopplerspektroskopie an einem Wasserstoffionenstrahl.
(DPG AMOP-Frühjahrstagung, 2007-03-19 to 2007-03-23,
Düsseldorf).
Zhang, D., L. Giannone, O. Grulke, M. Piechotka, T. Windisch,
A. Stark and T. Klinger: Investigation of the Neutral Gas Pressure
Effect on the Metal Resistive Bolometer. (PLASMA 2007 –
International Conference on Research and Applications of
Plasmas combined with the 4 th German-Polish Conference
on Plasma Diagnostics for Fusion and Applications and the
6 th French-Polish Seminar on Thermal Plasma in Space and
Laboratory, 2007-10-16 to 2007-10-19, Greifswald).
Lectures
173

ASDEX Upgrade Team
J. Adamek*, C. Angioni, G. Antar, C. V. Atanasiu*, M. Balden,
W. Becker, K. Behler, K. Behringer, A. Bergmann, T. Bertoncelli,
R. Bilato, V. Bobkov, O. Bottino, M. Brambilla, F. Braun,
M. Brüdgam, A. Buhler, A. Chankin, I. Classen, G. Conway,
D. P. Coster, P. de Marné, S. Dietrich, R. D’Inca, R. Drube,
R. Dux, T. Eich, K. Engelhardt, H.-U. Fahrbach, L. Fattorini*,
J. Fink, R. Fischer, A. Flaws, M. Foley*, C. Forest*,
J. C. Fuchs, K. Gál*, M. García Muñoz, M. Gemisic Adamov,
L. Gianonne, T. Görler, S. Gori, S. da Graca*, H. Greuner,
O. Gruber, A. Gude, S. Günter, G. Haas, J. Harhausen,
B. Heinemann, A. Herrmann, N. Hicks, J. Hobirk, M. Hölzl,
D. Holtum, C. Hopf, L. Horton, M. Huart, V. Igochine, F. Jenko,
A. Kallenbach, S. Kálvin*, O. Kardaun, M. Kaufmann,
M. Kick, A Kirk, H.-J. Klingshirn, G. Kocsis*, H. Kollotzek,
C. Konz, K. Krieger, T. Kurki-Suonio*, B. Kurzan, K. Lackner,
P. T. Lang, B. Langer, P. Lauber, M. Laux, F. Leuterer,
J. Likonen*, L. Liu, A. Lohs, A. Lyssoivan*, C. Maggi,
A. Manini, K. Mank, M.-E. Manso*, M. Mantsinen,
M. Maraschek, P. Martin*, M. Mayer, P. McCarthy*,
K. McCormick, H. Meister, F. Meo*, P. Merkel, R. Merkel,
V. Mertens, F. Merz, H. Meyer*, A. Mlynek, F. Monaco,
H. W. Müller, M. Münich, H. Murmann, G. Neu, R. Neu,
J. Neuhauser, B. Nold*, J.-M. Noterdaeme, G. Pautasso,
G. Pereverzev, E. Poli, M. J. Püschel, T. Pütterich, R. Pugno,
E. Quigley*, I. Radivojevic, G. Raupp, M. Reich, B. Reiter,
T. Ribeiro*, R. Riedl, V. Rohde, J. Roth, M. Rott, F. Ryter,
W. Sandmann, J. Santos*, K. Sassenberg, A. Scarabosio,
G. Schall, H.-B. Schilling, J. Schirmer, A. Schmid, K. Schmid,
W. Schneider, G. Schramm, R. Schrittwieser*, W. Schustereder,
J. Schweinzer, S. Schweizer, B. Scott, U. Seidel, M. Sempf,
F. Serra*, M. Sertoli, A. Sigalov, A. Silva*, A. C. C. Sips,
E. Speth, A. Stäbler, K.-H. Steuer, J. Stober, B. Streibl,
E. Strumberger, W. Suttrop, G. Tardini, C. Tichmann,
W. Treutterer, C. Tröster, L. Urso, E. Vainonen-Ahlgren*,
P. Varela*, L. Vermare, D. Wagner, C. Wigger, M. Wischmeier,
E. Wolfrum, E. Würsching, D. Yadikin, Q. Yu, D. Zasche,
T. Zehetbauer, M. Zilker, H. Zohm.
ECRH-Team
A. Arnold, B. Berndt, P. Brand, H. Braune, G. Dammertz,
V. Erckmann, J. Flamm, G. Gantenbein, M. Grünert,
R. Heidinger, F. Hollmann, M. Huber, H. Hunger, S. Illy, J. Jin,
L. Jonitz, W. Kasparek, S. Kern, M. Krämer, H. Kumric,
R. Lang, H. P. Laqua, C. Lechte, W. Leonhardt, O. Mangold,
D. Mellein, G. Michel, F. Müller, R. Munk, F. Noke, B. Piosczyk,
B. Plaum, S. Prets, O. Prinz, F. Purps, T. Rzesnicki,
U. Saller, P. Salzmann, K.-H. Schlüter, M. Schmid, T. Schulz,
W. Spiess, M. Stoner, U. Stroth, J. Szczesny, M. Thumm,
P. Uhren, J. Weggen, M. Weißgerber, D. Wimmer, C. Zöller.
Teams
175
ICRF-Team
S. Assas, W. Becker, V. Bobkov, F. Braun, R. D’Incà, B. Eckert,
R. Euteneier, H. Faugel, F. Fischer, L. Liu, M. Mantsinen*,
J.-M. Noterdaeme, A. Onyshchenko*, M. Prechtl, T. Sachse,
G. Siegl, H. Wehling, C. Wiesmann, E. Würsching, I. Zammuto.
NBI-Team
P. Agostinetti*, M. Berger, S. Christ-Koch, H. Falter, U. Fantz,
P. Franzen, M. Fröschle, R. Gutser, B. Heinemann, D. Holtum,
C. Hopf, T. Jiang*, R. Kairys, M. Kick, W. Kraus, S. Leyer,
C. Martens, P. McNeely, R. Nocentini, S. Obermayer, R. Riedl,
P. Rong, N. Rust, J. Schäffler, R. Schroeder, J. Sielanko*,
E. Speth, A. Stäbler, P. Turba, D. Wünderlich.
NNBI-Team
P. Agostinetti*, M. Berger, S. Christ-Koch, H. Falter, U. Fantz,
P. Franzen, M. Fröschle, R. Gutser, B. Heinemann, D. Holtum,
T. Jiang*, W. Kraus, S. Leyer, C. Martens, P. McNeely,
R. Nocentini, S. Obermayer, R. Riedl, J. Sielanko*, E. Speth,
P. Turba, D. Wünderlich.
W7-X Team
G. Adam, J. Ahmels, T. Andreeva, M. Balden, K. Bald-Soliman,
J. Baldzuhn, M. Banduch, H. Bau, Ch. Baylard*, W. Becker,
M. Bednarek, D. Beiersdorf, A. Benndorf, M. Bensouda-
Korachi, A. Berg, N. Berger, A. Bergmann, P. Biedunkiewicz,
R. Binder, D. Birus, T. Bluhm, R. Blumenthal, H. Bolt,
J. Boscary, H.-S. Bosch, B. Böswirth, A. Braatz, R. Brakel,
H.-J. Bramow, T. Bräuer, H. Braune, T. Broszat, B. Brucker,
R. Brüderl, R. Burhenn, V. Bykov, J. Cantarini*, A. Cardella*,
D. Chauvin*, P. Chen, W. Chen, G. Croari*, P. Czarkowski*,
M. Czerwinski, W. Dänner*, J. Dedic, C. Dhard, A. Dinklage,
A. Domscheidt, A. Dübner, A. Dudek, H. Dutz, B. Eckert,
P. v. Eeten, K. Egorov, G. Ehrke, H. Eixenberger, M. Endler,
V. Erckmann, H. Faugel, W. Fay, J.-H. Feist, J. Fellinger,
A. Friedrich, F. Fischer, N. Fuchs, F. Füllenbach, G. Gliege,
S. Gojdka, M. Gottschewsky, H. Greuner, H. Greve, P. Grigull,
H. Grote, D. Grünberg, H. Grunwald, L. Guerrini*, D. Gustke,
M. Haas, N. Hajnal, E. Hahnke, K.-H. Hanausch, A. Hansen,
H.-J. Hartfuß, D. Hartmann, D. Hathiramani, D. Haus,
P. Heimann, B. Hein, B. Heinemann, K. Henkelmann, C. Hennig,
U. Herbst, D. Hermann, F. Herold, K. Hertel, D. Hildebrandt,
M. Hirsch, A. Hölting, D. Holtum, A. Holtz, R. Holzthüm,
M. Huart, H. Hübner, A. Hübschmann, F. Hurd*, M. Ihrke,
N. Jaksic, D. Jassmann, H. Jenzsch, A. John, L. Jonitz, S. Jung,
A. Junge, P. Junghanns*, J. Kallmeyer, U. Kamionka,
M. Kammerloher, M. Kick, J. Kißlinger*, T. Kluck, C. Klug,
M. Kluger, J. Knauer, F. Koch, R. König, T. Koppe, M. Köppen,

P. Kornejev, R. Krampitz, R. Krause, U. Krybus, M. Krychowiak,
G. Kühner, F. Kunkel, B. Kursinski, B. Kurzan, A. Kus,
H. Laqua, H. Laqua, M. Laux, H. Lentz, M. Lewerentz, C. Li,
S. Lindig, J. Lingertat*, A. Lorenz, Jo. Maier, Jü. Maier,
C. Martens, G. Matern, P. McNeely, B. Mendelevitch, G. Michel,
B. Missal, H. Modrow, St. Mohr, L. Mollwo, T. Mönnich,
A. Müller, E. Müller, I. Müller, J. Müller, K. Müller, M. Müller,
H. Murmann, M. Nagel, D. Naujoks, U. Neumann, U. Neuner,
U. Nielsen*, M. Nitz, F. Noke, J. M. Noterdaeme, S. Obermayer,
A. Okkenga-Wolf, A. Opitz, E. Pasch, A. Peacock, B. Petersen-
Zarling, B. Petzold, K. Pfefferle, M. Pietsch, D. Pilopp, S. Pingel,
H. Pirsch, R. Pollner, R. Preuß*, F. Purps, D. Rademann,
T. Rajna *, H. Rapp*, J. Reich, L. Reinke, T. Richert, R. Riedl,
K. Riße, M. Rott, K. Rummel, Th. Rummel, N. Rust, N. Rüter,
J. Sachtleben, P.G. Sanchez*, J. Schacht, F. Schauer,
F. Scherwenke, D. Schinkel, R.-C. Schmidt, M. Schneider,
W. Schneider, M. Schrader, R. Schroeder, M. Schröder,
P. Scholz, U. Schultz, A. Schütz, E. Schwarzkopf, S. Schweizer,
Ch. von Sehren, K.-U. Seidler, G. Siegl, J. Simon-Weidner,
W. Sinz, B. Sitkowski, M. Smirnow, E. Speth, A. Spring,
A. Stäbler, R. Stadler, F. Starke, M. Steffen, B. Streibl,
M. Sochor, L. Sonnerup*, A. Tereshchenko, D. Theuerkauf,
S. Thiel, H. Tittes, R. Tivey, P. Turba, H. Thomsen, V. Tomarchio*,
P. Uhren, S. Valet, A. Vetterlein, H. Viebke, T. Vierle,
R. Vilbrandt, O. Volzke, S. Vorbrugg, A. Vorköper, F. Wagner,
M. Wanner, S. Weber, L. Wegener, M. Weißgerber, A. Weller,
J. Wendorf, S. Wendorf*, U. Wenzel, A. Werner, K.-D. Wiegand,
M. Winkler, R. Wolf, M. Ye, D. Zacharias, G. Zangl, F. Zeus,
D. Zhang, M. Zilker, K. Zimmermann.
*external authors
Teams
176

Appendix

Stuttgart A8
Appendix
How to reach IPP in Garching
Garmisch
Lindau
A9 6
A9 5
A9 9
Nürnberg
Exit
Garching
Nord
S1
A9
U6
178
Neufahrn
München
Bus 690
Garching
S8
By car:
Exit Garching-Nord on the
Autobahn A9 München-Nürnberg,
then follow the signs “Forschungsinstitute”.
A8
Garching-
Research Center
Passau
A9 4
Salzburg
By public transport:
Any S metro from Munich Main Station to Marienplatz,
metro U6 to Garching-Forschungszentrum;
or from Airport Munich: S1 to Neufahrn, then bus 690
to "Garching Forschungszentrum" (only on weekdays).
A92
A9 9
Deggendorf
A9 9
Munich Airport

Direction
Rostock
Appendix
How to reach Greifswald Branch Institute of IPP
Exit
Greifswald
BAB
A20
B96
Exit
Gützkow
DB
Greifswald
179
B105
Direction
Neubrandenburg
Berlin
Greifswald
Centre
B109
DB
Exit
Schönwalde
By air and train:
Via Berlin: from Berlin Tegel Airport by bus “JetExpressBus” to Hauptbahnhof (central station),
by train to Greifswald.
Via Hamburg: from the airport to main Railway Station, by train to Greifswald main station.
By bus:
From Greifswald-Railway Station by bus No. 2 or 3 to the “Elisenpark” stop.
By car:
Via Berlin, Neubrandenburg to Greifswald or via Hamburg, Lübeck, Stralsund to Greifswald,
in Greifswald follow the signs “Max-Planck-Institut”.
L35
B109
Direction
Anklam

Appendix
Organisational structure
of Max-Planck-Institut für Plasmaphysik
180

Max-Planck-Institut
für Plasmaphysik