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High heat flux behaviour of damaged plasma facing components

F Escourbiac, P Chappuis, J Schlosser, M Merola, M Febvre2001年Fusion Engineering and DesignIF 1.7出版社

AbstractA 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.

日本語訳

ITERダイバータ垂直ターゲットの中規模プロトタイプであって、較正された内部接合欠陥を有するものを、赤外線特性評価、熱疲労試験、および有限要素解析により試験・研究した。欠陥検出のためのツールと、これらの欠陥の供用期間中の挙動を本稿で提示する。

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Plasma-facing component
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