作为核研究堆候选燃料的铀钼合金的生产

G. K. Suryaman, M. W. Wildan, Supardjo Supardjo, Yatno Dwi Agus Susanto
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引用次数: 1

摘要

铀钼合金作为核研究堆候选燃料的生产。用于核研究堆燃料的高密度铀的研究和开发仍在进行中。铀钼合金是核研究堆最有力的候选燃料材料之一。铀钼合金的性能和特性是燃料生产工艺选择的重要考虑因素。本文采用电弧熔炼技术成功制备了不同钼含量的铀钼合金。钼含量变化为7% wt, 8% wt, 9% wt和10% wt Mo。熔炼过程进行5次以达到均匀化。金相显微图显示存在枝晶组织。XRD检测结果证实了γ-U相和d-U2Mo相的存在。显微硬度维氏试验表明,钼含量越高的铀钼合金硬度值越高。关键词:铀钼合金,研究堆,燃料。
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PRODUCTION OF URANIUM-MOLYBDENUM ALLOY AS A CANDIDATE FOR NUCLEAR RESEARCH REACTOR FUEL
PRODUCTION OF URANIUM−MOLYBDENUM ALLOY AS A CANDIDATE FOR NUCLEAR RESEARCH REACTOR FUEL. Research and development on high density uranium for nuclear research reactor fuel is still in progress. Uranium-molybdenum alloy is one of the strongest candidates of nuclear research reactor fuel material. The properties and characteristics of U-Mo alloy is of important consideration for the selction of the fabrication techniques for the production of  the fuel. In this work, uranium-molybdenum (U-Mo) alloys with varied molybdenum content have been produced succesfully by arc melting technique. The molybdenum content variations were 7 %wt, 8 %wt, 9 %wt and 10 %wt Mo. The melting process was done 5 times to achieve homogenization. Metallographic micrograph shows the presence of dendritic structure. XRD examination result affirms the presence of 2 phases of γ-U phase and d-U2Mo phase. Microhardness Vickers test shows higher hardness value for Uranium-molybdenum alloy with higher molybdenum content.Keywords: U−Mo alloy, research reactor, fuel.
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