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Crack propagation in first wall of fusion reactor by cyclic thermal stress

S. Kimura, H. Kogawa, T. Teramoto, M. Saito1998年Fusion Engineering and DesignIF 1.7出版社

AbstractTo clarify the crack propagation behavior of first wall materials under high thermal load cycles, cyclic high heat flux loading tests were carried out on SUS316. A specimen with a thickness of 5 mm was used, and the tests were performed under three types of external load conditions in order to investigate the effect of stationary tensile stress, simulating gravitational load on the first wall. To get rid of the effect of creep, the duration time of the beam was limited to 0.5 s in every 30 s high heat flux loading cycle. Two-dimensional thermal and elasto-plastic stress analyses and non-linear fracture mechanics analysis were carried out, and the fatigue crack propagation lengths were evaluated using Ĵ-integral amplitude ΔĴeff. Through this study, it was concluded that crack propagation lengths were decreased by applying stationary moderate tensile load, and that the evaluated crack lengths roughly agreed with experimental ones.

日本語訳

第一壁材料の高熱負荷サイクル下におけるき裂進展挙動を明らかにするため、SUS316を用いて高熱流束繰返し負荷試験を実施した。試験には厚さ5mmの試験片を用い、第一壁に作用する重力負荷を模擬した定常引張応力の影響を調べるため、3種類の外部負荷条件下で試験を行った。クリープの影響を排除するため、高熱流束負荷サイクル1回あたりの負荷時間は30秒間のうち0.5秒に制限した。二次元熱弾塑性応力解析および非線形破壊力学解析を実施し、J積分範囲ΔĴeffを用いて疲労き裂進展長さを評価した。本研究により、定常的な中程度の引張応力を負荷することでき裂進展長さが減少すること、および評価されたき裂長さが実験結果と概ね一致することが明らかとなった。

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