A new look at JET operation with Be as plasma facing material

被引:20
作者
Loarte, A
Saibene, G
Sartori, R
Campbell, DJ
Lomas, PJ
Matthews, GF
机构
[1] EFDA, Close Support Unit, D-85748 Garching, Germany
[2] UKAEA Euratom Fus Assoc, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
关键词
JET; beryllium; plasma facing components; ITER; thermal load; liquid metal;
D O I
10.1016/j.jnucmat.2004.09.038
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Experiments at JET with Be as plasma-facing material demonstrate that although Be PFCs are easily damaged, the consequences for plasma operation are mild. L-mode plasmas up to a current of 7 MA and heating power similar to 30 MW were obtained on heavily damaged Be limiter with similar to 12 MJ plasma energy, albeit with a very high Be content. The behaviour of H-mode plasmas in contact with a molten Be divertor target was studied. Despite the heavy damage to the target (similar to 3 turn molten grooves) no plasma performance deterioration was observed for medium density ELMy H-modes. Type I ELMs, in these conditions, lead to similar to 40 mu m melt layer formation but to an average melt layer loss of only similar to 4%. Based on these results, conclusions for ITER limiter and divertor operation are extracted. (c) 2004 Published by Elsevier B.V.
引用
收藏
页码:816 / 820
页数:5
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