Heat flux depositions on the WEST divertor and first wall components

被引：28

作者：

Firdaouss, M. ^{[1
]}

Batal, T. ^{[1
]}

Bucalossi, J. ^{[1
]}

Languille, P. ^{[1
]}

Nardon, E. ^{[1
]}

Richou, M. ^{[1
]}

机构：

[1] CEA, IRFM, F-13108 St Paul Les Durance, France

来源：

FUSION ENGINEERING AND DESIGN | 2015年 / 98-99卷

关键词：

Heat flux; Plasma facing components; Simulation; Ripple effect;

D O I：

10.1016/j.fusengdes.2014.12.024

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The primary goal of the WEST project is to be a test-bed for ITER W divertor components, in terms of manufacturing issues as well as fatigue and lifetime regarding thermal loads during operations. Therefore it is necessary to ensure that the thermal loads available in Tore Supra are of the same magnitude as those expected for ITER. It is also necessary to ensure that the other plasma facing components would not be a limitation to reach this target. On this basis, simulations of the incident heat flux on the main components have been done for different parameters. Those simulations are done with PFCFlux code and include the variation of the toroidal magnetic field called ripple effect. This paper reports the results of those simulations and concludes on the usability of the plasma facing components with the required heat loads. (C) 2015 Elsevier B.V. All rights reserved.

引用

页码：1294 / 1298

页数：5

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