原子炉圧力容器用確率論的破壊力学解析コードPASCAL ver. 2の開発 Development of Probabilistic Fracture Mechanics Analysis Code PASCAL ver. 2 for Reactor Pressure Vessel

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  As a part of the materials aging degradation and structural integrity research for LWR components, the probabilistic fracture mechanics (PFM) analysis code PASCAL has been developed in JAEA. This code evaluates the conditional probabilities of crack initiation and fracture of a reactor pressure vessel (RPV) under transient conditions such as pressurized thermal shock (PTS). A standardized analysis method is proposed on the basis of the development of PASCAL ver. 2 and results of sensitivity analyses. Graphical user interface (GUI) including the standardized analysis method as default settings and values has been also developed for PASCAL ver. 2. A case study showed that non-destructive examination with good performance had a more significant effect on the probability of failure than non-destructive examinations repeated with low performance.<br>

収録刊行物

  • 日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan  

    日本原子力学会和文論文誌 = Transactions of the Atomic Energy Society of Japan 6(2), 161-171, 2007-06-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10018763597
  • NII書誌ID(NCID)
    AA11643165
  • 本文言語コード
    JPN
  • 資料種別
    ART
  • ISSN
    13472879
  • NDL 記事登録ID
    8884273
  • NDL 雑誌分類
    ZN36(科学技術--原子力工学・工業)
  • NDL 請求記号
    Z74-C788
  • データ提供元
    CJP書誌  CJP引用  NDL  J-STAGE 
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