A shaped First Wall for ITER

被引:30
作者
Mitteau, R. [1 ]
Stangeby, P. [2 ]
Lowry, C. [3 ]
Firdaouss, M. [4 ]
Labidi, H. [4 ]
Loarte, A. [1 ]
Merola, M. [1 ]
Pitts, R. [1 ]
Raffray, R. [1 ]
机构
[1] ITER Org, F-13067 St Paul Les Durance, France
[2] Univ Toronto, Inst Aerosp Studies, N York, ON M3H 5T6, Canada
[3] Culham Sci Ctr, EFDA CSU, Abingdon OX14 3DB, Oxon, England
[4] Assytem, F-84120 Pertuis, France
关键词
PLASMA-FACING COMPONENTS; THERMAL RESPONSE; MODEL; TRANSIENTS; RACLETTE;
D O I
10.1016/j.jnucmat.2010.10.070
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The ITER First Wall is being redesigned to address a number of issues identified during the 2007 design review. One of the main improvements concerns the handling of parallel plasma heat loads. The design must be optimised for maximum leading edge protection with acceptable power flux distribution, which is achieved by shaping the First Wall panels. The conceptual design presented in the paper can accommodate both inboard and outboard limiter plasmas for a total power in the discharge of 7.5 MW at 7.5 MA and allows the abandonment of the original dedicated port limiters. (C) 2010 Published by Elsevier B.V.
引用
收藏
页码:S969 / S972
页数:4
相关论文
共 7 条
[1]   RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients .2. Analysis of ITER plasma facing components [J].
Federici, G ;
Raffray, AR .
JOURNAL OF NUCLEAR MATERIALS, 1997, 244 (02) :101-130
[2]   CONTOURING OF AN INERTIALLY COOLED PUMP LIMITER FOR TORE SUPRA [J].
KOSKI, JA ;
DEMPSEY, JF ;
MCGRATH, RT .
FUSION ENGINEERING AND DESIGN, 1992, 15 (03) :263-277
[3]  
Loarte A., 2008, 22 IAEA FUS EN C GEN
[4]   Heat flux deposition on plasma-facing components using a convective model with ripple and Shafranov shift [J].
Mitteau, R ;
Moal, A ;
Schlosser, J ;
Guilhem, D .
JOURNAL OF NUCLEAR MATERIALS, 1999, 266 :798-803
[5]  
Mitteau R., P ISFNT 9 C IN PRESS
[6]   RACLETTE: A model for evaluating the thermal response of plasma facing components to slow high power plasma transients .1. Theory and description of model capabilities [J].
Raffray, AR ;
Federici, G .
JOURNAL OF NUCLEAR MATERIALS, 1997, 244 (02) :85-100
[7]   Analysis for shaping the ITER first wall [J].
Stangeby, P. C. ;
Mitteau, R. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 390-91 :963-966