High heat flux behaviour of damaged plasma facing components

被引：9

作者：

Escourbiac, F ^{[1
]}

Chappuis, P

Schlosser, J

Merola, M

Vastra, I

Febvre, M

机构：

[1] CEA, EURATOM Assoc, DRFC, F-13108 St Paul Les Durance, France

[2] EFDA Close Support Unit, D-85748 Garching, Germany

[3] Framatome France, Ctr Tech, F-71200 Le Creusot, France

来源：

FUSION ENGINEERING AND DESIGN | 2001年 / 56-57卷

关键词：

prototype; vertical target; infrared characterisation; fatigue testing;

D O I：

10.1016/S0920-3796(01)00301-5

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：

A medium scale prototype of the ITER divertor vertical target, manufactured with calibrated internal bonding defects is tested and studied via infrared characterisation, thermal fatigue testing and finite element analysis. Tools for defect detection and behaviour of these defects along in-service lifetime are presented in this document. (C) 2001 Published by Elsevier Science B.V.

引用

页码：285 / 290

页数：6