Melting Temperature of Irradiated Fast Reactor Mixed Oxide Fuels

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The melting (solidus) temperatures of irradiated mixed oxide fuels were measured and the compositions of the fuels on the temperature measurement date were calculated. The fuels contained about 29wt% Pu initially and were irradiated up to 124GWd/t in the experimental fast reactor JOYO. A melting temperature correlation was obtained by an experimental regression analysis using 21 measurements:<BR>Τ<SUB>m</SUB>=3, 133.8-460Χ<SUB>1</SUB>-980Χ<SUB>2</SUB>-0.66Χ<SUB>3</SUB>+0.0013(Χ<SUB>3</SUB>)<SUP>2</SUP>, <BR>where Τ<SUB>m</SUB>, is the expected melting temperature (K), Χ<SUB>1</SUB> the plutonium fraction (Pu/(Pu+U)) and Χ<SUB>2</SUB> the americium fraction (Am/(Pu+U+Am)) at the measurement, and Χ<SUB>3</SUB> the burnup (GWd/t). The equation shows that the melting temperature decreases by 5, 4, and 3K per 10GWd/t at 50, 100 and 150GWd/t, respectively. The effects of actinides, such as Pu and Am, on melting temperature could be explained by an ideal solution model. However, the decreases caused by soluble fission products could not be well explained in terms of the ideal solution model.

収録刊行物

  • Journal of nuclear science and technology  

    Journal of nuclear science and technology 35(7), 494-501, 1998-07-25 

    Atomic Energy Society of Japan

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各種コード

  • NII論文ID(NAID)
    10002079728
  • 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
    4525686
  • 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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