Impact on the amount of high-level waste of minor actinide in combination with americium transmutation and TRU generation reduction UO2 fuel in BWR

IF 2.3 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Annals of Nuclear Energy Pub Date : 2025-06-15 Epub Date: 2025-02-27 DOI:10.1016/j.anucene.2025.111308

Kouji Hiraiwa , Rei Kimura , Satoshi Wada , Tsukasa Sugita , Kenichi Yoshioka , Satoshi Takeda , Takanori Kitada

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Abstract

We performed americium transmutation in uranium fuel with a transuranic generation reduction fuel, which uses BWR fuel and increases the ²³⁵U enrichment within the range of High-Assay Low-Enriched Uranium (HALEU). We evaluated the relationship between the total decay heat of ²⁴¹Am and ²⁴⁴Cm. The increase in decay heat from ²⁴⁴Cm when the ²³⁵U enrichment is 3.8 wt%, which is the example case of LEU application as that of existing fuel. The generation of ²⁴⁴Cm comes from a smaller mass number of TRU nuclides decrease as the neutron flux and neutron capture reactions decrease with increasing enrichment. As a result, in the range where the enrichment exceeds about 7.5 wt%, and the ratio of the decrease in the weight fraction of ²⁴¹Am to the increase in the weight fraction of ²⁴⁴Cm decreases below 4.1 %, and the total decay heat of the two nuclides is lower than it would be in no-transmutation.

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微量锕系元素与镅嬗变及TRU生成减少UO2燃料联合对沸水堆高放废物量的影响

采用超铀生成还原燃料对铀燃料进行了镅嬗变，该燃料使用沸水堆燃料，在高含量低浓缩铀（HALEU）范围内提高了235U的富集度。我们评估了241Am的总衰变热与244Cm的关系。当235U富集为3.8 wt%时，衰变热从244Cm增加，这是低浓铀应用于现有燃料的例子。随着中子通量和中子俘获反应的减少，TRU核素的质量数随着富集的增加而减少，从而产生244Cm。因此，在富集超过7.5 wt%的范围内，241Am质量分数的下降与244Cm质量分数的增加之比减小到4.1%以下，两种核素的总衰变热低于未发生嬗变时的衰变热。

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来源期刊

Annals of Nuclear Energy 工程技术-核科学技术

CiteScore

4.30

自引率

21.10%

发文量

632

审稿时长

7.3 months

期刊介绍： Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.