High-density U-Mo fuel for research reactors

High-density U-Mo fuel for research reactors
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研究堆用高密度 U-Mo 燃料

DOI：
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发表时间：
2004
期刊：
影响因子：
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通讯作者：
Y. Trifonov
Y. Trifonov
中科院分区：
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文献类型：
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作者：
A. Vatulin;A. Morozov;V. B. Suprun;Y. Petrov;Y. Trifonov

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研究了主要合金元素（钼含量为1.5～9wt.%）和铝、硅、锡添加剂对研究堆弥散核燃料用铀合金的结构、相组成和性能的影响。确定了确保合金结构稳定的热处理参数。研究了含钼和含钼锡添加剂的铀合金中第二相的偏析。确定了在基体中提供 UAl2 和 U5Sn4 颗粒精细偏析的最佳热处理参数。研究结果用于开发一种组合物，用于制造用于反应堆测试的燃料砂粒和分散燃料。
The effect of the content of the main alloying element (molybdenum in an amount of from 1.5 to 9 wt.%) and of additives of aluminum, silicon, and tin on the structure, phase composition, and properties of uranium alloys used as dispersion nuclear fuel in research reactors is studied. The heat treatment parameters ensuring a stable structure in the alloys are determined. Segregation of secondary phases in uranium alloys with molybdenum and molybdenum and tin additives is studied. Heat treatment parameters optimum for providing fine segregations of UAl2 and U5Sn4 particles in the matrix are determined. The results of the study are used to develop a composition for fabricating fuel grit and dispersion fuel for reactor tests.