Nuclear aspects of diagnostics in RTO/RC ITER

被引:5
|
作者
Walker, CI
Yamamoto, S
Costley, A
deKock, L
Ebisawa, K
Janeschitz, G
Khripunov, V
Martin, E
Vayakis, G
机构
[1] ITER Joint Cent Team, Divertor & Plasma Interface Div, D-85748 Garching, Germany
[2] ITER, Naka, Ibaraki 3110193, Japan
关键词
radiation environment; diagnostic design; ex-vessel remote handling; in-vessel remote handling;
D O I
10.1016/S0920-3796(00)00299-4
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
ITER (international thermonuclear experimental reactor) will be the first fusion device where the design of the plasma diagnostic systems will make extensive use of the materials and techniques developed in the nuclear technology held. The designs have to satisfy stringent requirements for tritium confinement, nuclear shielding and vacuum integrity. This paper introduces the requirements for diagnostics in the ITER long pulse, burning plasma environment, and addresses the impact of the reactor environment on the diagnostics and ancillary equipment. These systems necessarily require access to the plasma or first wall, which generally conflicts with the requirements of the basic machine. Holes are required through the first wall, primary shielding, containment boundaries and biological shielding. Components have a limited life and require maintenance. This paper describes the effect of the radiation environment on diagnostic design at different locations. Ex-vessel and in-vessel remote handling, hot cell refurbishment and tritium confinement are also described. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:377 / 385
页数:9
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