Modified formula for the assessment of the thermal response of neutron irradiated CFC

被引：2
作者：
Barabash, V
Snead, LL
机构：
[1] INER, Int Team, D-85748 Garching, Germany
[2] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
来源：
JOURNAL OF NUCLEAR MATERIALS | 2004年 / 329卷
关键词：
D O I：
10.1016/j.jnucmat.2004.04.215
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The available thermal conductivity data for various neutron-irradiated 2-3 dimensional carbon fibre composite materials have been collected and have been critically reviewed with respect to possible application in the ITER divertor. The empirical correlations are proposed that match the thermal conductivity data and allow interpolate or extrapolate of the behaviour in the wide temperature (similar to150-3000 degreesC) and fluence (0-0.1 dpa) ranges of interest for ITER. These include the correlations for materials with 'high' ( greater than or similar to 200 W/m K) initial thermal conductivity and for materials with moderate (similar to100 W/mK) thermal conductivity. Using the proposed formula the thermal performance of CFC armoured ITER divertor is assessed. (C) 2004 Published by Elsevier B.V.
引用
收藏
页码：860 / 864
页数：5
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