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

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It measures back-scattered radiation using the other ECRH<br />

antenna and transmission line located in the same port. This<br />

information will be used to infer the 1-D velocity distribution<br />

of the confined fast ions.<br />

The figure 17 above shows the first scattered radiation results,<br />

an important milestone for the diagnostic. The centre most<br />

channels are plotted as a function of time during a plasma<br />

discharge where the receiver antenna is swept twice across<br />

the gyrotron beam. The vertical lines are the time points<br />

where the receiver antenna position is expected to have<br />

maximum overlap. The commissioning is in its final stages<br />

and physics exploitation is expected in the 2008 campaign.<br />

6.7 Radial acceleration of solid hydrogen pellets<br />

Fuelling pellets, injected into the plasma from the magnetic<br />

high field side (HFS), undergo a strong radial acceleration<br />

towards the magnetic low field side (LFS), as observed by a<br />

fast framing camera system. The camera images allow for the<br />

study of the pellet velocity through the whole pellet trajectory<br />

inside the separatrix, revealing a monotonic increase of the<br />

acceleration as the pellet penetrates deeper into the plasma.<br />

The cause of this radial acceleration is thought to originate<br />

from a rocket-effect by the asymmetric ablation of the pellet<br />

surface. The ablation asymmetry is the result of the grad B<br />

drift of the pellet cloud, which is then shifted relative to the<br />

pellet. As the pellet cloud provides shelter for the pellet from<br />

hot plasma electrons, the shift of the cloud towards the LFS<br />

will result in a higher heat flux (i.e. a higher ablation rate) at<br />

the HFS of the pellet, thus there will be a net reaction force on<br />

the pellet caused by the impulse of the leaving particles.<br />

Simulations, based on the simple but yet most powerful pellet<br />

ablation model, the NGS (Neutral Gas Shielding), were performed<br />

to estimate the ablation asymmetry. It was assumed<br />

that the total ablation rate is given by the NGS model, but a<br />

small fraction (ε) of it is asymmetrically produced on the<br />

pellet’s HFS. The corresponding net radial force on the pellet<br />

and hence acceleration is taken into account in the simulation,<br />

resulting in curved pellet trajectories similar to the measurements.<br />

Simulations were performed with pellet and injection<br />

geometry settings identical to those in the measurements.<br />

The asymmetry parameter (ε) was tuned until the simulated<br />

pellet trajectory fitted the measured one separately for each<br />

pellet event, and the corresponding value of ε was considered<br />

as the output of the simulation. Up to now 16 pellet events have<br />

been studied and asymmetry values fell in the range of 3-9 %.<br />

6.8 New stochastic model for the sawtooth crash<br />

The sawtooth oscillation is one of the fundamental instabilities<br />

observed in tokamaks. Still no definitive explanation for<br />

the crash process exists. Incomplete sawtooth reconnection<br />

is often observed. It is associated with an internal m/n=1/1<br />

kink mode which does not vanish after the crash phase (as<br />

would be the case for complete reconnection).<br />

ASDEX Upgrade<br />

16<br />

It was shown that these sawteeth cannot be fully described<br />

by a pure m/n=1/1 mode and that higher harmonics play an<br />

important role during the sawtooth crash phase. We demonstrated<br />

that stochastization appears due to the excitation of<br />

low-order resonances which are present in the corresponding<br />

q-profiles inside the q=1 surface which reflects the key<br />

role of the central q(0)-value. Depending on this value two<br />

completely different situations are possible for one and the<br />

same mode perturbations: (i) the resonant surfaces are present<br />

in the q-profile leading to stochasticity and sawtooth crash<br />

(q(0)=0.7±0.1); (ii) the resonant surfaces are not present,<br />

which means no stochasticity in the system and no crash<br />

event (q(0)=0.9±0.05). Accordingly the central safety factor<br />

value is always less than unity in the case of a non-complete<br />

sawtooth reconnection. Our investigations show that the stochastic<br />

model agrees well with the experimental observations<br />

and can be proposed as a promising candidate for an<br />

explanation of the sawtooth reconnection.<br />

6.9 Extrapolation of AUG H-mode discharges to ITER<br />

Scaling laws predict ITER’s confinement and fusion performance<br />

in H-mode. Besides the well established IPB98(y,2)<br />

law, others have been proposed with a weaker β dependence,<br />

such as Cordey’s (2005) and the GyroBohm scaling laws<br />

(see figure 18).<br />

Q/(Q+5)<br />

1<br />

0.1<br />

0.05<br />

IPB98(y,2) Cordey05<br />

0.1 1<br />

3.23 -1.23 -3.10<br />

35.5 H β q<br />

98 N 95<br />

ES GB<br />

ITER ITER<br />

ITER<br />

0.1 1 0.1 1<br />

1.82 0.18 -2.20<br />

6.07 H Cor β N q 95<br />

2.22 -0.22 -2.71<br />

22.8 H EGB β N q95<br />

Figure 18: 0D figure of merit of Q/(Q+5) assuming a constant Greenwald<br />

fraction for the different scaling laws, versus Q/(Q+5) predicted with the 1D<br />

ASTRA simulations. IPB98(y,2) (red), Cordey 05 (green), GyroBohm (blue)<br />

Theory based dimensionless models also predict the ITER<br />

performance. However, even those based on the same instabilities<br />

yield different core predictions. Moreover they are<br />

strongly sensitive to the pedestal density and temperatures,<br />

which are predicted with large uncertainties. In this work<br />

we extrapolate AUG discharges to ITER, using the information<br />

contained in the scaling laws with additional input<br />

from present experiments, in particular the profile shapes,<br />

the H factors, the thermal normalised pressure β N,th and q 95 .<br />

A profile database of 92 well diagnosed H-mode discharges<br />

has been selected, including only stationary time intervals.<br />

The scaled profiles have then been used for ASTRA simulations<br />

with ITER geometry, in order to predict the P fus and P rad ,<br />

as well as P aux needed to obtain the target β N,th at the given<br />

H-factor. The effect of varying the tungsten concentrations<br />

is also investigated here. Dimensionless figures of merit are

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