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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >Actinide mixed oxide conversion by advanced thermal denitration route
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Actinide mixed oxide conversion by advanced thermal denitration route

机译:通过先进的热脱硝路线的Actinide混合氧化物转换

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摘要

In the framework of generation IV development for nuclear reactors, actinide mixed oxides are considered for multirecycling plutonium fuels and for transmutation targets of minor actinides. In this context, new processes are being developed for either the synthesis of mixed uranium-plutonium oxide compounds for MOx fuel or uranium-americium target fabrications. The main purposes are to simplify and step up industrial processes as well as to decrease actinide dust dispersion, and liquid effluent and gaseous releases. Among options for conversion route, a novel and patented advanced thermal denitration in presence of organic additives was established successfully to synthesize UO2+delta, U0.55Pu0.45O2 +/-delta, and U0.9Am0.1O2-delta oxides. Here, we describe the different intermediate steps of this process together with the characterization of the oxides obtained. The data highlight several advantages of this new route for actinide conversion. (C) 2019 Elsevier B.V. All rights reserved.
机译:在核反应堆的第四代发展框架中,抗肌细胞混合氧化物被认为是多碳钚燃料和轻微神光型的嬗变靶标。 在这种情况下,正在开发新方法,用于合成MOX燃料或铀 - 美靶制品的混合铀 - 钚氧化物化合物。 主要目的是简化和介绍工业过程,以及减少散落粉尘分散和液体流出物和气体释放。 在转化途径选择中,成功地建立了有机添加剂存在的新颖和专利的先进热脱硝,以合成UO2 + Delta,U0.550.45O2 +/-Δ和U0.9AM0.1O2-δ氧化物。 这里,我们将该方法的不同中间步骤与所获得的氧化物的表征一起描述。 数据突出了这一新路线的几个优势,以实现滑动转换。 (c)2019 Elsevier B.v.保留所有权利。

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