Behavior of Nb_2O_5 Doped/Unpressurized UO_2 Fuel under Transient

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著者

    • YANAGISAWA Kazuaki
    • Nuclear Safety Research Center, Tokai Research Establishment, Japan Atomic Energy Research Institute

抄録

This paper describes the results of reactivity initiated accident (RIA) experiments using unpressurized UO<SUB>2</SUB> fuel pellets containing 0.30 wt% Nb<SUB>2</SUB>O<SUB>5</SUB> additive. From the result of postpulse-irradiation examination (PIE) such as visual inspection, dimensional measurement and metallo/ceramography, fuel failure threshold and failure mechanism were explored. The results obtained were: (1) Failure threshold of the Nb<SUB>2</SUB>O<SUB>5</SUB> doped fuel was almost equal to that of NSRR standard fuel rod data, which were adopted in the Licensing Guideline for RIA, Japan. (2) Failure mechanism of the Nb<SUB>2</SUB>O<SUB>5</SUB> doped fuel under unpressurized condition was cladding melt followed by enbrittlement of thinned cladding wall. No significant difference in the failure mechanism existed between the doped and undoped fuels. Bonding is not peculiar to the doped fuel, namely occurred at lower value of deposited energy (276cal/g•fuel) in the doped fuel than that (341cal/gfuel) in the undoped fuel. (3) No measurable difference in the threshold for mechanical energy release existed between Nb<SUB>2</SUB>O<SUB>5</SUB> doped fuel rod and NSRR standard fuel rods. (4) Axial elongation in the unpressurized doped fuels was significantly greater than that in prepressurized doped ones.

収録刊行物

  • Journal of nuclear science and technology

    Journal of nuclear science and technology 32(2), 111-117, 1995-02-25

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002072029
  • 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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