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Wiesen, S.; Kalupin, D.; Parail, V.; Corrigan, G.; Fundamenski, W.; Zagorski, R.
JET EFDA group
Conference presentation2007
JET EFDA group
Conference presentation2007
AbstractAbstract
[en] Neutral transport across the SOL into the edge of the core plasma has an effect on different fields of edge physics research. It was shown for example that gas puffing from outside can have an effect on the power threshold for the LH-transition because it is strongly dependent on the fraction of radial convective to conductive heat losses. Thus, the window in which ITER can be operated in an ELMy H-mode is dependent on neutral transport and there is the question for optimisation. Experimentally, it was seen that the ELM frequency can be increased and the ELM amplitude decreases with increasing gas-puffing rate from the outside and a transition from type-I to type-III ELMs could be achieved with the positive effect for the power deposition onto the walls and targets but also degrades the energy confinement. Moderate energy losses in the edge due to charge-exchange processes with the neutrals might be responsible for this and the ETB itself can be affected. Thus, gas-puffing can be a candidate for controlling the ELM behaviour. Recently, it was shown that simple models like the Engelhardt-Mahdavi model which simply equates the particle transport equations of neutrals and the plasma in radial direction are not adequate enough to resemble the whole density pedestal structure including open and closed field lines. Thus, two-dimensional numerical modelling is needed in most cases for a better characterisation of the ETB and its plasma profiles including pressure gradients with consistently varying transport coefficients. This work presents the results of a systematic study of the numerical characterisation of the ETB for JET with the EDGE2D/EIRENE code package. Recently, the kinetic neutral transport Monte-Carlo code EIRENE was coupled to EDGE2D to replace NIMBUS to benefit from EIRENE's more sophisticated features (improved A(and)M model, geometry flexibility). Fully predictive simulations are very time-consuming, thus the problem is tackled via changing the radial transport coefficient profiles used in EDGE2D by hand and density scans with varying gas-puffing rates from different poloidal positions are done. A complete understanding of the full non-linear problem may be achieved by coupling to a transport code (i.e. JETTO or RITM) to have a self-consistent view of the effect of neutral transport on the ETB which is a subject of a future work. (author)
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Source
[33 p.]; 2007; 1 p; IEA Large Tokamak IA Workshop on Edge Transport in Fusion Plasmas; Cracow (Poland); 11-13 Sep 2006; Also available at http://www.ifpilm.waw.pl; 3 refs.
Record Type
Miscellaneous
Literature Type
Conference
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CLOSED PLASMA DEVICES, COMPUTER CODES, CONFINEMENT, DIFFERENTIAL EQUATIONS, EQUATIONS, INSTABILITY, INTEGRO-DIFFERENTIAL EQUATIONS, KINETIC EQUATIONS, MAGNETIC CONFINEMENT, PARTIAL DIFFERENTIAL EQUATIONS, PLASMA CONFINEMENT, PLASMA INSTABILITY, PLASMA MACROINSTABILITIES, SIMULATION, THERMONUCLEAR DEVICES, THERMONUCLEAR REACTORS, TOKAMAK DEVICES, TOKAMAK TYPE REACTORS
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