Transient Behavior of Waterside Corroded PWR Fuel

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A behavior of waterside corroded PWR fuels under transient conditions was studied. In order to simulate the corroded condition, unpressurized test fuel rods having cladding oxidation up to 80μm and hydrogen contents up to 344ppm in maximum were fabricated and pulse irradiated in the Nuclear Safety Research Reactor (NSRR) belonged to the Japan Atomic Energy Research Institute.<BR>Major results obtained are:<BR>(1) The waterside corroded fuel rods having oxides to the magnitude of 50, 60, 70 and 80μm did not fail in the energy deposition range from 256 to 279 cal/g•fuel. The value was exceeded the failure threshold of 260cal/g•fuel for NSRR standard fuel. While, the reference (no oxide) fuel rods in the same energy deposition range failed by melt/brittle of the cladding followed by wrinkle deformation.<BR>(2) From posttransient irradiation examination it was found that wrinkle deformation in the waterside corroded fuels occurred very little due to rather relatively low cladding surface temperature and small diametral residual strain than those in the reference fuels.

収録刊行物

  • Journal of nuclear science and technology

    Journal of nuclear science and technology 32(4), 313-320, 1995-04-25

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002072373
  • 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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