Transient Behavior of Low Enriched Uranium Silicide and Aluminide Miniplate Fuel for Research Reactors

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This paper describes the results of transient experiments using a low enriched uranium silicide (density, 4.0g U/cm<SUP>3</SUP>) and aluminide (density, 2.2g U/cm<SUP>3</SUP>) miniplate fuels prepared for the Japan Research Reactor-3 (JRR-3). The transient irradiation was performed in the Nuclear Safety Research Reactor (NSRR) at the Japan Atomic Energy Research Institute (JAERI). The results obtained are summarized below.<BR>(1) The tested silicide miniplate fuel, which will be a candidate for a future low enriched fuel in the JRR-3 core, did not fail with an energy deposition of 106cal/g•fuel at a peak cladding surface temperature (PCST) of 508°C. This condition simulated a transient causing blister failure, which was assumed to occur above the PCST of 400°C. Accordingly, the tested silicide miniplate fuel had a strong resistance against blistering up to 508°C.<BR>(2) The tested aluminide miniplate fuel did not fail with an energy deposition of 55cal/g•fuel at a PCST of 230°C. This condition simulated an accidental water channel closure, which was assumed in the safety analysis of JRR-3. The predicted PCST by using the EUREKA-2 code was about 150°C. Accordingly the conventional aluminide fuel used in JRR-3 was found to be intact under a simulated water channel closure accident.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 32(9), 889-897, 1995-09-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002073173
  • 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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