Application of Simplified Condensation Model to PWR LBLOCA Transient Analysis with TRAC-PF1 Code

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著者

    • AKIMOTO Hajime
    • Department of Reactor Engineering, Japan Atomic Energy Research Institute
    • MURAO Yoshio
    • Department of Reactor Engineering, Japan Atomic Energy Research Institute

抄録

In the system analyses of a large-break loss-of-coolant accident (LBLOCA) of pressurized water reactors (PWRs), the TRAC-PF1 code predicted an unrealistic depressurization and required much computational time due to the problem of the condensation model. To eliminate the unrealistic depressurization, the TRAC-PF1 code was improved using a simplified condensation model that determined the total condensation rate at cold leg. Through the assessment calculations for CCTF, UPTF and LOFT tests, it was confirmed that the simplified model could eliminate the unrealistic depressurization and reduce the computational time. It was also confirmed that the model could improve the accuracy of the system calculation for the core inlet flow rate and clad temperature as the result of the elimination of the unrealistic depressurization. It has been concluded that the simplified condensation model is useful for the system calculation of the. PWR LBLOCA.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 33(4), p.290-297, 1996-04-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002074559
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • データ提供元
    CJP書誌  J-STAGE 
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