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Mechanical behavior of graphite first wall during disruptions

J. Ohmori, T. Kobayashi, M. Yamada, H. Iida, T. Horie1989年Fusion Engineering and DesignIF 1.7出版社

The mechanical behavior of graphite first wall armor during plasma disruptions was examined by applying fracture mechanics concepts. A fracture mechanics approch is suitable for lifetime evaluation, because the armor surface is expected to be damaged by intense heat load. Two stages are supposed for the lifetime of the armor: crack initiation and crack propagation, which are related to the fatigue life and the energy release rate, respectively. The terms are calculated for the disruption conditions of the Fusion Experimental Reactor (FER), which is referred to as a post JT-60 machine. The analytical results indicate that even though some damage is expected on the armor surface after a few disruptions, unstable failure does not necessarily occur for all disruption conditions.

日本語訳

黒鉛第一壁アーマの機械的挙動は、破壊力学の概念を適用することにより、プラズマディスラプション中に検討された。破壊力学アプローチは、アーマ表面が強い熱負荷によって損傷を受けると予想されるため、寿命評価に適している。アーマの寿命については、き裂発生とき裂進展の2つの段階が想定され、これらはそれぞれ疲労寿命とエネルギー解放率に関連している。これらの項は、JT-60の後継機として言及される核融合実験炉(FER)のディスラプション条件に対して計算される。解析結果は、数回のディスラプション後にアーマ表面に何らかの損傷が予想されるものの、すべてのディスラプション条件において不安定破壊が必ずしも発生するわけではないことを示している。

装置

jt-60sa低精度(概要文一致)

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Plasma disruptionFirst wall
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