Wall protection strategies for DEMO plasma transients

被引:41
|
作者
Maviglia, F. [1 ,2 ]
Albanese, R. [2 ]
Ambrosino, R. [2 ]
Arter, W. [3 ]
Bachmann, C. [1 ]
Barrett, T. [3 ]
Federici, G. [1 ]
Firdaous, M. [4 ]
Gerardin, J. [4 ]
Kovari, M. [3 ]
Loschiavo, V. [2 ]
Mattei, M. [2 ]
Villone, F. [2 ]
Wenninger, R. [1 ]
机构
[1] EUROfus Consortium, PPPT Dept, Boltzmannstr 2, Garching, Germany
[2] Consorzio CREATE, Via Claudio 21, I-80125 Naples, Italy
[3] Culhom Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England
[4] CEA, IRFM, F-13108 St Paul Les Durance, France
关键词
DEMO; Heat wall load; Plasma facing components; Transient loads; 1ST WALL; DESIGN;
D O I
10.1016/j.fusengdes.2018.02.064
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 present DEMO breeding blanked design heat load capability is limited to approximate to 1 MW/m(2) for steady state plasma loading, due to the specific requirements on high neutron irradiation capable materials, and high coolant temperature for efficient energy conversion. While this limit is achievable in nominal conditions in the present DEMO blanket concept designs, the greatest challenges arise from the occurrence of plasma transients. The results of simulations of a number of plasma transients are presented in this paper. 3D field-line tracing codes have been used to analyses the maximum heat flux and energy density for a specific first wall shape design, and optimize it. A scoping study has been performed with the thermal analysis code RACLETTE, using a broad range of transient input heat fluxes, on a series of high heat flux (HF) components concepts with tungsten armor, Eurofer steel or copper alloy as heat sink materials, and helium or water as coolant. The results permit the identification of the operational space of the peak HF density that can be tolerated by different plasma facing components, for the different transient models.
引用
收藏
页码:410 / 414
页数:5
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