Nonlinear Fracture Mechanics Analysis of Surface Crack Propagation in Fusion Reactor First Wall by Cyclic High Heat Flux Irradiation

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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.

収録刊行物

  • Journal of nuclear science and technology

    Journal of nuclear science and technology 34(2), 128-136, 1997-02-25

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002076399
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • NDL 記事登録ID
    4153646
  • NDL 雑誌分類
    ZM35(科学技術--物理学)
  • NDL 請求記号
    Z53-A460
  • データ提供元
    CJP書誌  NDL  J-STAGE 
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