Thorium-uranium close fuel cycle in fluoride-salt-cooled solid-fuel fast reactor with two recycle strategies,International Journal of Energy Research

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Thorium-uranium close fuel cycle in fluoride-salt-cooled solid-fuel fast reactor with two recycle strategies
International Journal of Energy Research ( IF 4.3 ) Pub Date : 2020-11-23 , DOI: 10.1002/er.6168
Yu Peng _{1,

2} , Guifeng Zhu ₂ , Yang Zou ₂ , Hongjie Xu ₂

Affiliation

Fluoride-salt-cooled solid-fuel fast reactor (LSFR) based on thorium fuel could achieve a self-sustaining core which satisfies long term energy supply. In this paper, we further investigated the LSFR core neutronics characteristics for the close fuel cycle from the 0th cycle core to the 8th cycle core. Two fuel recycle schemes, including U recycling and U/Pu/MA recycling, were put forward to evaluate physical effects caused by these recycling elements. It was found that both closed fuel recycle schemes gained self-sustaining core and reduced the ²³³U fuel loading, indicating that recycling nuclides could partially replace ²³³U. Due to the lower ²³³U loading in fuel cycle process, the breeding performance of LSFR core was better and U/Pu/MA recycling scheme possessed more advantages. The LSFR core could not transmute MA due to the relatively soft fast energy spectrum. The U/Pu/MA recycle scheme accumulated more transuranium elements with cycle burnup than that of U recycle scheme.

中文翻译：

含两种循环策略的氟盐冷却固体燃料快堆中钍铀闭式燃料循环

基于钍燃料的氟化盐冷却固体燃料快堆（LSFR）可以实现满足长期能源供应的自持堆芯。在本文中，我们进一步研究了从第 0 次循环堆芯到第 8 次循环堆芯的封闭燃料循环的 LSFR 堆芯中子学特性。提出了两种燃料回收方案，包括 U 回收和 U/Pu/MA 回收，以评估这些回收元素造成的物理效应。发现两种封闭式燃料循环方案都获得了自持堆芯并减少了²³³ U 燃料负荷，表明循环核素可以部分替代²³³ U。由于较低的²³³ UU在燃料循环过程中加载，LSFR堆芯的增殖性能更好，U/Pu/MA回收方案更具优势。由于相对较软的快速能谱，LSFR 核心无法转换 MA。U/Pu/MA 回收方案比 U 回收方案积累了更多具有循环燃耗的超铀元素。

更新日期：2020-11-23

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