Transient Elongation of a Fresh Fuel Rod under Reactivity Initiated Accident Conditions

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著者

    • ISHIJIMA Kiyomi
    • Reactivity Accident Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Research Institute
    • NAKAMURA Takehiko
    • Reactivity Accident Laboratory, Department of Reactor Safety Research, Japan Atomic Energy Research Institute

抄録

In-pile experiments of fresh fuel rods under reactivity initiated accident (RIA) conditions have been performed in the Nuclear Safety Research Reactor at the Japan Atomic Energy Research Institute in order to understand the basic pellet cladding mechanical interaction (PCMI) behavior. Rapid fuel pellet expansion due to a power excursion would cause radial and longitudinal deformation of the cladding. This PCMI could be one of the possible incipient failure modes of an embrittled cladding of a high burnup fuel under the RIA conditions. <BR>Basic PCMI behavior was studied by measuring cladding deformation of a fresh fuel rod without complicated irradiation effects. The transient elongation measurements of the fuel with two kinds of gap width indicated not only PCMI-induced cladding elongation, but also reduction of the pellet stack displacement by the cladding constraint. In the tests under a high-pressure and high-temperature condition simulating an operation condition of BWRs, additional ridge-type cladding deformation was generated due to the axial collapse of the cladding. A preliminary analysis for interpretation of the tests was made using a computer code for the transient analysis of fuel rods, FRAP-T6.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 33(3), p.229-238, 1996-03-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002074400
  • 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  CJP引用  J-STAGE 
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