Enhancement of CsI Aerosol Size in Superheated Steam in Reactor Piping under Severe Accidents

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It is recognized in the source term evaluation of light water reactors that large uncertainties still remain in the fission products aerosol behavior in reactor coolant system during severe accidents<SUP>(1)</SUP>. Especially the aerosol size distribution has a great impact on the deposition behavior onto the inner surface of pipe wall through several mechanisms such as gravitational sedimentation and impaction. The present analytical models<SUP>(2)(3)</SUP> used in source term evaluation consider the growth of aerosol size due to steam condensation onto aerosol particles. However the effect of condensation is neglected in superheated steam. In an early stage of severe accident sequence the generated FP aerosol will be transported to primary circuit by superheated steam. Therefore it is essential to evaluate the aerosol size distribution under superheated steam. In the present experiments, the CsI gas and aerosol behaviors at a PWR hot leg inlet was simulated and the effect of difference in carrier gas, nitrogen and steam, on the CsI behavior in pipe was investigated.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 33(10), p.804-806, 1996-10-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002075691
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    NOT
  • ISSN
    00223131
  • NDL 記事登録ID
    4079947
  • 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  CJP引用  NDL  J-STAGE 
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