Nonlinear Fracture Mechanics Analysis of Surface Crack Propagation in Fusion Reactor First Wall by Cyclic High Heat Flux Irradiation
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概要
- 論文の詳細を見る
Crack generation and propagation through the first wall of a fusion reactor under cyclic thermal stress caused by pulsed reactor operation has been studied analytically, and the results have been compared with experimentally acquired data. The analysis first covered the transient heat transfer through a test specimen pulse-heated on one face and constantly cooled on the reverse face. This was followed by elastoplastic stress analysis to estimate the stress-strain relation that prevails during pulsed heating. Finally, the crack propagation behavior was analyzed applying the non-linear fracture mechanics parameter termed "extended J-integral", and calculated with the three-dimensional finite element code "MARC". The results agreed well with experimental data obtained on a test specimen of type 316 stainless steel plate that was subjected to cyclic electron beam heating. This indicated the possibility of validly predicting the crack propagation behavior of a fusion reactor first wall.
- 社団法人 日本原子力学会の論文
- 1997-02-25
著者
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Saito Masaki
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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Teramoto Tokuo
University Of Tokyo
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Teramoto Tokuo
University Of Tsukuba
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Saito Masakatu
Research Laboratory For Nuclear Reactors Tokyo Institute Of Technology
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SUGAYA Akihito
University of Tsukuba
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SAITO Masakatu
University of Tsukuba
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NISHIMURA Toshinori
Nikko Superior Metal Corp.
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