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The Effects of Plutonium Content and Self-Irradiation on Thermal Conductivity of Mixed Oxide Fuel

机译:Content含量和自辐照对混合氧化物燃料导热系数的影响

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摘要

This study evaluated the effects of plutonium content and self-irradiation on the thermal conductivity of mixed oxide (MOX) fuel. Samples of UO2 fuel and various MOX fuels were tested. The MOX fuels had a range of plutonium contents, and some samples were stored for 20 years. The thermal conductivity of these samples was determined from thermal diffusivity measurements taken via laser flash analysis. Although the thermal conductivity decreased with increasing plutonium content, this effect was slight. The effect of self-irradiation was investigated using the stored samples. The reduction in thermal conductivity caused by self-irradiation depended on the plutonium content, its isotopic composition, and storage time. The reduction in thermal conductivity over 20 year's storage can be predicted from the change of the lattice parameter. In addition, the decrease in thermal conductivity caused by self-irradiation was recovered with heat treatment-and was recovered almost completely at temperatures over 1200 K. From these evaluation results, we formulated an equation for thermal conductivity that is based on the classical phonon-transport model. This equation can predict the thermal conductivity of MOX fuel thermal conductivity by accounting for the influences of plutonium content and self-irradiation.
机译:这项研究评估了content含量和自辐照对混合氧化物(MOX)燃料导热系数的影响。测试了UO2燃料和各种MOX燃料的样品。 MOX燃料具有一定范围的p含量,一些样品可以保存20年。这些样品的热导率由通过激光闪光分析获得的热扩散率测量值确定。尽管随着conductivity含量的增加,导热系数降低,但这种影响很小。使用储存的样品研究了自照射的效果。自辐照引起的热导率降低取决于depend的含量,其同位素组成和储存时间。可以通过晶格参数的变化来预测在20年的存储过程中导热系数的降低。此外,由于自辐照引起的热导率下降可以通过热处理得到恢复,并且在1200 K以上的温度下几乎可以完全恢复。根据这些评估结果,我们建立了基于经典声子的热导率方程。运输模型。该方程可以通过考虑p含量和自辐照的影响来预测MOX燃料的热导率。

著录项

  • 来源
    《Nuclear Technology》 |2019年第3期|474-485|共12页
  • 作者单位

    Japan Atom Energy Agcy, 4-33 Muramatsu, Tokai, Ibaraki 3191194, Japan;

    Japan Atom Energy Agcy, 4-33 Muramatsu, Tokai, Ibaraki 3191194, Japan;

    Japan Atom Energy Agcy, 4002 Narita Cho, Oarai, Ibaraki 3111393, Japan;

    Japan Atom Energy Agcy, 4-33 Muramatsu, Tokai, Ibaraki 3191194, Japan;

    Univ Fukui, Res Inst Nucl Engn, 1-3-33 Kanawachou, Turuga City 9140055, Japan;

  • 收录信息 美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

    Mixed oxide fuel; plutonium; thermal conductivity; self-irradiation;

    机译:混合氧化物燃料;p;热导率;自辐照;
  • 入库时间 2022-08-18 04:06:34

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