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

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Tokamak Physics Division<br />

Head: Prof. Dr. Sibylle Günter<br />

Tokamak Edge Physics Group<br />

Work in the group has balanced<br />

the use of existing codes to understand<br />

phenomena in the edge plasma<br />

(or to identify discrepancies<br />

between code and experiment),<br />

and the improvement of the codes.<br />

Current edge codes form an important<br />

bridge between results<br />

on present machines and divertor operation on ITER. The<br />

present ITER divertor is based to a large extent on the results<br />

of simulations with one of the existing edge codes, while a<br />

number of edge codes are in use to understand present day<br />

experimental results. To place the ITER predictions on a<br />

firmer footing, an effort has been made to verify the existing<br />

codes by careful code-code comparison, and then to validate<br />

the codes against the experiment. This is done within the<br />

framework of an ITPA DivSOL activity (DSOL-14), and<br />

also as part of the activities of the EU Task Force on<br />

Integrated Tokamak Modelling. In 2004, the results of the<br />

EDGE2D-NIMBUS, B2-EIRENE (SOLPS5) comparison<br />

for the D only case were reported together with some preliminary<br />

results with drifts. During the <strong>2007</strong> JET edge modelling<br />

campaign, these results were extended to D+C for<br />

SOLPS, and some results for D and D+C for EDGE2D-<br />

NIMBUS and EDGE2D-EIRENE were also obtained. One<br />

of the major results was a renewed look at the atomic<br />

physics being used in the edge codes. For one particular<br />

case, the peak target electron temperature was found to<br />

change by a factor of nearly 10 depending on the choice of<br />

atomic physics (for hydrogen).<br />

In-depth examination of earlier identified discrepancies<br />

between SOLPS modelling and AUG experimental data was<br />

continued. Three types of discrepancies – in the divertor<br />

electron temperature T e , radial electric field E r and Mach<br />

numbers of parallel ion flow in the main scrape-off layer<br />

(SOL) M || – were linked together. A consistent picture of the<br />

problems encountered by the code modelling has been confirmed.<br />

The leading assumption about the origin of the discrepancies<br />

is the neglect of kinetic effects in the parallel electron<br />

heat transport from the SOL to divertor. Analysis of publications<br />

related to the role of kinetic effects in the SOL reveals<br />

a significant effect which they can have on the electron distribution<br />

function near the target, resulting in higher parallel<br />

electron heat flux and a large Debye sheath drop at the target.<br />

Work has started on developing a kinetic treatment for the<br />

edge plasma, with the intention of either coupling this to B2,<br />

or to try to parameterize the results in some fashion for<br />

inclusion in the fluid plasma code. In continuation of a project<br />

on disruptions at JET, a series of modified pre-disruptive<br />

Theoretical Plasma Physics<br />

Head: Prof. Dr. Per Helander<br />

The project “Theoretical Plasma Physics” is devoted<br />

to first-principle based model developments<br />

and combines the corresponding efforts of<br />

the divisions Tokamak Physics and Stellarator<br />

Theory, of the Junior Research Groups “Turbulence<br />

in Magnetized Plasmas”, “Theory and Ab Initio<br />

Simulation of Plasma Turbulence”, and “Computational<br />

Material Science”, and the EURYI Research<br />

Group “Zonal Flows”. It is headed by one theorist<br />

on the board of scientific directors at a time.<br />

81<br />

JET equilibria has been subjected<br />

to thermal quench modelling<br />

with the SOLPS package.<br />

Development of version 6.0 of<br />

the SOLPS package supporting<br />

adaptive mesh refinement has<br />

continued. Based on the current<br />

implementation of the B2 fluid<br />

code, approaches to implement a<br />

generalized framework for the solution<br />

of the fluid equations have<br />

been studied. The main focus lies<br />

on higher-order schemes for conservation laws on unstructured<br />

quadrilateral meshes and efficient data structures enabling<br />

later parallelization of core components of the code.<br />

Other work included: (1) continuing activities associated<br />

with the EFDA Task Force on Integrated Tokamak Modelling;<br />

(2) maintenance, support, and further development of<br />

the SOLPS code; (3) supporting the use of SOLPS at <strong>IPP</strong> to<br />

(i) explore the differences between L- and H-mode edge profiles<br />

in terms of the derived transport coefficients, (ii) explore<br />

the impact of a killer gas puff on AUG, and (iii) explore the<br />

process of detachment.<br />

MHD Theory Group<br />

Heat Transport in Magnetic Islands<br />

Heat diffusion studies using a recently developed numerical<br />

scheme were continued. For cylindrical geometry, heat diffusion<br />

across magnetic islands and ergodic layers has been<br />

studied in detail. The effect of the observed island temperature<br />

flattening on the stability of Neoclassical Tearing Modes<br />

was examined. It was found that the neoclassical island drive<br />

is significantly stronger for realistic island parameters than<br />

predicted by Fitzpatrick 1 .<br />

A new code has been implemented which applies the numerical<br />

scheme to toroidal geometries using straight field line<br />

coordinates. First results for magnetic islands and ergodic<br />

layers in realistic ASDEX Upgrade equilibria suggest that<br />

cases with realistic heat diffusion anisotropies can be very<br />

well resolved.<br />

Fully Three-dimensional Resistive Wall Mode and Feedback<br />

Stabilization Studies<br />

The feedback stabilization of Resistive Wall Modes (RWMs)<br />

has been studied in the presence of multiply connected wall<br />

structures using the fully three dimensional CAS3D, STAR-<br />

WALL, and OPTIM codes. The coupling of toroidal modes<br />

in 3D has been taken into account. The codes have been<br />

applied to an ITER and an ASDEX Upgrade like equilibrium<br />

with β N =2.51 and β N =2.62, respectively. For both cases stable<br />

solutions have been found.<br />

1 R. Fitzpatrick, Physics of Plasmas 2, 825 (1995)

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