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首页> 外文期刊>Journal of Alloys and Compounds: An Interdisciplinary Journal of Materials Science and Solid-state Chemistry and Physics >Effect of molybdenum addition on metastability of cubic 7-uranium
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Effect of molybdenum addition on metastability of cubic 7-uranium

机译：钼对立方7-铀亚稳性的影响

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摘要

Over the years U_3Si_2 compound dispersed in aluminium matrix has been used successfully as the potential low enriched uranium (LEU<20%U~(235)) base dispersion fuel for use in new research and test reactors and also for converting high enriched uranium (HEU>85%U~(235)) cores to LEU for most of the existing research and test reactors world over, though maximum 4.8 gU cm~(-3) density is achievable with U_3Si_2-Al dispersion fuel. To achieve a uranium density of 8.0-9.0 g U cm~(-3) in dispersion fuel with aluminium as matrix material, it is required to use γ-stabilized uranium metal powders. At Bhabha Atomic Research Centre (BARC), R&D efforts are on to develop these high density uranium base alloys. This paper describes the alloying behaviour of uranium with varying amount of molybdenum. The U-Mo alloys with different molybdenum content have been prepared by using an induction melting furnace with uranium and molybdenum metal pellets as starting materials. U-Mo alloys with different molybdenum content were characterized by X-ray diffraction (XRD) for phase identification and lattice parameter measurements. The optical microstructure of different U-Mo alloy composition has also been discussed in this paper. Quantitative image analysis was also carried out to determine the amount of various phases in each composition.
机译：多年来，已成功地将分散在铝基质中的U_3Si_2化合物用作潜在的低浓铀（LEU <20％U〜（235））基础分散燃料，用于新的研究和测试反应堆以及转化高浓铀（HEU）尽管大多数U_3Si_2-Al分散燃料可实现最大4.8 gU cm〜（-3）的密度，但全世界大多数现有研究和测试反应堆的LEU堆芯中> 85％U〜（235））的密度都很高。为了在以铝为基质材料的分散燃料中获得8.0-9.0 g U cm〜（-3）的铀密度，需要使用γ稳定化的铀金属粉末。在Bhabha原子研究中心（BARC），正在进行研发工作，以开发这些高密度铀基合金。本文描述了铀与不同钼含量的合金化行为。通过使用感应熔炉以铀和钼金属粒料为原料，制备了钼含量不同的U-Mo合金。通过X射线衍射（XRD）对具有不同钼含量的U-Mo合金进行表征，以进行相识别和晶格参数测量。本文还讨论了不同U-Mo合金成分的光学显微组织。还进行了定量图像分析以确定每种组合物中各个相的量。

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