現行の原子炉圧力容器の健全性評価手法に対するPASCAL ver. 2を用いた確率論的検討 Probabilistic Evaluation of Current Structural Integrity Assessment Method for Reactor Pressure Vessel Using PASCAL ver. 2

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  Fifty-five nuclear power plants of light water reactors (LWRs) in Japan including seven plants which have already reached a 30-year operation have been operated as of September 2006. The probabilistic fracture mechanics (PFM) method has been recently highlighted to rationally incorporate the uncertainties arising from the material properties, defect distribution, inspection quality and so on, unlike the conventional deterministic method. As a part of the materials aging degradation and structural integrity research for LWR components, the 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). Sensitivity analyses for pre-service and in-service inspections have been performed according to JSME S NA1-2004 and the correlation between the results by deterministic analysis according to the JEAC 4206-2004 and probabilistic analysis based on PFM for the integrity of RPV under PTS has also been described.<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), 172-182, 2007-06-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10018763625
  • 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
    8884289
  • 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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