Critical heat flux analysis and RED for the design of the ITER divertor

被引:145
作者
Raffray, AR [1 ]
Schlosser, J
Akiba, M
Araki, M
Chiocchio, S
Driemeyer, D
Escourbiac, F
Grigoriev, S
Merola, M
Tivey, R
Vieider, G
Youchison, D
机构
[1] EURATOM, Max Planck Inst Plasmaphys, ITER Garching JWS, D-85748 Garching, Germany
[2] CEA Cadarache, Dept Rech Fus Controlee, EURATOM Assoc, F-13108 St Paul Durance, France
[3] JAERI, Naka, Ibaraki 3110193, Japan
[4] Boeing, St Louis, MO 63166 USA
[5] ATEM, F-13009 Marseille, France
[6] Efremov Inst, STC SINTEZ, St Petersburg 189631, Russia
[7] EURATOM, Max Planck Inst Plasmaphys, Net Team, D-85748 Garching, Germany
[8] Sandia Natl Labs, Fus Technol Dept, Albuquerque, NM 87185 USA
关键词
ITER; divertor; critical heat flux; mock-up testing;
D O I
10.1016/S0920-3796(99)00053-8
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 vertical target and dump target of the ITER divertor have to be designed for high heat fluxes (up to 20 MW/m(2) over approximate to 10 s). Accommodation of such high heat fluxes gives rise to several issues, including the critical beat flux (CHF) margin which is a key requirement influencing the choice of cooling channel geometry and coolant conditions. An R&D programme was evolved to address the overall CHF issue and to help focus the design. It involved participation of the four ITER home teams and has been very successful in substantially expanding the CHF data base for one-sided heating and in providing more accurate experimental measurements of pressure drop (and derived correlations) for these geometries. This paper describes the major R&D results and the design analysis performed in converging on a choice of reference configuration and parameters which resulted in a CHF margin of approximate to 1.4 or more for all divertor components. (C) 1999 Elsevier Science Ireland Ltd. All rights reserved.
引用
收藏
页码:377 / 407
页数:31
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