am掺杂UO2嬗变靶的制备

Gamze Colak , Tommy Mai
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引用次数: 0

摘要

核能是产生大量电力的二氧化碳排放量最少的方式之一。核能利用的一个主要挑战是乏核燃料的管理。放射性毒性较小的锕系元素,特别是Am (<;0.1 wt%的乏燃料),可以通过分割和嬗变提取和回收。一种创新的,无尘的方法来生产(U,Am)O2-x目标,而不产生Am污染的液体废物已经成功证明。该方法包括以淀粉为成孔剂,低温煅烧,通过内部凝胶法制备多孔氧化铀微球(UO3)。焙烧后的UO3微球采用单步浸渍法,用Am(NO3)3水溶液浸渍。浸渍后对微球进行干燥、煅烧和烧结。分别制备了Am含量为5、10、20、30 mol%的样品。微观结构研究表明,煅烧后多孔宿主微球的密度约为65% TD,可达孔隙率为30 vol%,适合有效渗透。对(U,Am)O2-x微球的横截面检测显示Am和U混合均匀,没有形成明显掺杂水平的团聚体。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Fabrication of Am-doped UO2 transmutation targets

Fabrication of Am-doped UO2 transmutation targets
Nuclear energy is one of the least CO2 emitting ways of generating large amounts of electricity. One major challenge in the utilization of nuclear energy is the management of spent nuclear fuel. The radiotoxic minor actinides, particularly Am (< 0.1 wt% of spent fuel), could be extracted and recycled via partitioning and transmutation. An innovative, dust-free method for producing (U,Am)O2-x targets without the generation of Am-contaminated liquid waste has been successfully demonstrated. The method comprises the fabrication of porous uranium oxide microspheres (UO3) through internal gelation, using starch as a pore-former and low-temperature calcination. After calcination of UO3 microspheres were infiltrated using a single-step process with aqueous Am(NO3)3. After infiltration, the microspheres were dried, calcined and sintered. Various samples targeting Am contents of 5, 10, 20 and 30 mol% were prepared. The microstructural investigations revealed that the density of the porous host microspheres after the calcination was approximately 65 %TD with 30 vol% accessible porosity, suitable for an efficient infiltration. The examination of cross-sectioned (U,Am)O2-x microspheres revealed homogeneous mixing of Am and U, without formation of agglomerates with distinct doping levels.
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