Thermal Conductivity Measurements on UO_<2+x> from 300 to 1, 400 K

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In order to evaluate the thermal conductivity of oxidized fuel pellets of leaker fuel rods, UO<SUB>2+x</SUB> samples with x between 0.00 and 0.20 were prepared by an oxidation or a sintering method. Sample thermal diffusivities were measured by using a laser flash method from 300 to 1, 400K and their thermal conductivities were evaluated from multiplying the thermal diffusivities by the sample densities and the specific heat capacities derived from the literature. The thermal conductivities of UO<SUB>2+x</SUB> were decreased with increasing hyperstoichiometry and they were expressed as a function of their hyperstoichiometry using the concentration of U<SUB>5+</SUB> formed with the excess interstitial oxygen atoms.

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  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 33(8), p.636-640, 1996-08-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002075265
  • NII書誌ID(NCID)
    AA00703720
  • 本文言語コード
    ENG
  • 資料種別
    ART
  • ISSN
    00223131
  • NDL 記事登録ID
    4060417
  • 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  NDL  J-STAGE 
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