Plasma boundary and first-wall diagnostics in ITER

被引:0
|
作者
Pitcher, C. S. [1 ]
Andrew, P. [1 ]
Barnsley, R. [1 ]
Bertalot, L. [1 ]
Counsell, G. G. [2 ]
Encheva, A. [1 ]
Feder, R. E. [3 ]
Hatae, T. [4 ]
Johnson, D. W. [3 ]
Kim, J. [1 ]
Kusama, Y. [4 ]
Lee, H. G. [5 ]
Mukhin, E. E. [6 ]
Reichle, R. [1 ]
Thomas, D. M. [1 ]
Tugarinov, S. N. [7 ]
Udintsev, V. S. [1 ]
Vasu, P. [8 ]
Vayakis, G. [1 ]
Walker, C. I. [1 ]
Walsh, M. J. [1 ]
Yang, Q. W. [9 ]
Yatsuka, E. [4 ]
Zhao, J. [10 ]
Zvonkov, A. V. [11 ]
机构
[1] ITER Org, CS 90 046, F-13067 St Paul Les Durance, France
[2] F4E, Barcelona, Spain
[3] PPPL, Princeton, NJ USA
[4] JAEA, Naka, Ibaraki, Japan
[5] NFRI, Taejon, South Korea
[6] AF Ioffe Phys Tech Inst, St Petersburg 194021, Russia
[7] TRINITI, Troitsk, Moscow Oblast, Russia
[8] IPR, Gandhinagar, Gujarat, India
[9] SWIP, Chengdu, Sichuan, Peoples R China
[10] IPP, Hefei, Anhui, Peoples R China
[11] Kurchatov Inst, Moscow, Russia
关键词
DIVERTOR;
D O I
10.1016/j.jnucmat.2011.01.111
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
ITER plasma boundary and first-wall diagnostics are summarized in terms of their physical implementation and physics motivation. The challenge of extracting diagnostic signals while maintaining nuclear shielding is discussed, as well as the problems associated with high levels of erosion and redeposition. (C) 2011 Published by Elsevier B.V.
引用
收藏
页码:S1127 / S1132
页数:6
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