Development and Assessment of the COBRA/RELAP5 Code

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<BR>The COBRA/RELAP5 code has been developed to combine the realistic three-dimensional reactor vessel model of COBRA-TF with RELAP5/MOD3.2, thus to produce an advanced system analysis code with a multidimensional thermal-hydraulic module. This paper provides the integration scheme of the two codes. The results of developmental assesments are also provided, which include single channel tests, manometric flow oscillation problem, THTF Test 105, and LOFT L2-3 large break loss-of-coolant experiment. From the single channel tests, the integration scheme was proven to be valid. Other simulation results showed good agreement with the experimental data. The computational speed was also satisfactory. Therefore, the assessment confirmed that the COBRA/RELAP5 code can be a promising tool for analysis of complicated, multimensional, two-phase flow system transients.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 34(11), 1087-1098, 1997-11-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002078440
  • 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
    4346186
  • 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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