Scaling of ITER divertor parameters - interpolation from 2D modelling and extrapolation

被引:31
|
作者
Pacher, HD
Kukushkin, AS
Pacher, GW
Janeschitz, G
机构
[1] INRS Energie Mat & Telecommun, Varennes, PQ, Canada
[2] ITER, Joint Cent Team, Garching, Germany
[3] Inst Rech Hydro Quebec, Varennes, PQ J3X 1S1, Canada
[4] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany
关键词
ITER; divertor; plasma; tokamak; B2-EIRENE; ASTRA;
D O I
10.1016/S0022-3115(02)01374-0
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Detailed modelling studies of the divertor plasma for ITER have been carried out. Using these results, scaling relationships are developed linking SOL power, density, throughput, pumping speed, peak divertor power load, and helium density for ITER conditions in order to systematise the results and to extrapolate them beyond the range presently covered by the simulations. The key parameter for the scalings is the neutral pressure in the divertor. Both peak power load and helium density vary as the square of the power at constant pressure. The inclusion of helium elastic collisions reduces the helium density and leads to a steeper reduction with increasing pressure. Variants of the input conditions, i.e. different geometry, no helium elastic collisions, carbon walls, are also discussed, the consistency of the edge modelling with conditions required in the core is treated, and extrapolation to higher power operation is carried out. (C) 2003 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:657 / 663
页数:7
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