Comparison of the minor actinide transmutation efficiency in models of a fast neutron uranium-thorium fueled reactor

V. Korobeinikov, V. Kolesov, A. Mikhalev
{"title":"Comparison of the minor actinide transmutation efficiency in models of a fast neutron uranium-thorium fueled reactor","authors":"V. Korobeinikov, V. Kolesov, A. Mikhalev","doi":"10.3897/nucet.8.82757","DOIUrl":null,"url":null,"abstract":"In terms of nuclear raw materials, the issue of involving thorium in the fuel cycle is hardly very relevant. However, in view of the large-scale nuclear power development, the use of thorium seems to be quite natural and reasonable. The substitution of traditional uranium-plutonium fuel for uranium-thorium fuel in fast neutron reactors will significantly reduce the production of minor actinides, which will make it attractive for the transmutation of long-lived radioactive isotopes of americium, curium and neptunium that have already been and are still being accumulated.\n Due to the absence of uranium-233 in nature, the use of thorium in the nuclear power industry requires a closed fuel cycle. At the initial stage of developing the uranium-thorium cycle, it is proposed to use uranium-235 instead of uranium-233 as nuclear fuel.\n Studies have been carried out on the transmutation of minor actinides in a fast neutron reactor in which the uranium-thorium cycle is implemented. Several options for the structure of the core of such a reactor have been considered. It has been shown that heterogeneous placement of americium leads to higher rates of its transmutation than homogeneous placement does.","PeriodicalId":100969,"journal":{"name":"Nuclear Energy and Technology","volume":"78 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2022-03-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"1","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Energy and Technology","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.3897/nucet.8.82757","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 1

Abstract

In terms of nuclear raw materials, the issue of involving thorium in the fuel cycle is hardly very relevant. However, in view of the large-scale nuclear power development, the use of thorium seems to be quite natural and reasonable. The substitution of traditional uranium-plutonium fuel for uranium-thorium fuel in fast neutron reactors will significantly reduce the production of minor actinides, which will make it attractive for the transmutation of long-lived radioactive isotopes of americium, curium and neptunium that have already been and are still being accumulated. Due to the absence of uranium-233 in nature, the use of thorium in the nuclear power industry requires a closed fuel cycle. At the initial stage of developing the uranium-thorium cycle, it is proposed to use uranium-235 instead of uranium-233 as nuclear fuel. Studies have been carried out on the transmutation of minor actinides in a fast neutron reactor in which the uranium-thorium cycle is implemented. Several options for the structure of the core of such a reactor have been considered. It has been shown that heterogeneous placement of americium leads to higher rates of its transmutation than homogeneous placement does.
在快中子铀-钍燃料反应堆模型中微量锕系元素嬗变效率Comparison
就核原料而言,将钍纳入燃料循环的问题几乎无关紧要。然而,考虑到核电的大规模发展,钍的使用似乎是相当自然和合理的。在快中子反应堆中,用传统的铀-钚燃料代替铀-钍燃料将大大减少少量锕系元素的产生,这对已经积累和仍在积累的镅、curium和镎的长寿命放射性同位素的嬗变具有吸引力。由于自然界中不存在铀-233,在核电工业中使用钍需要一个封闭的燃料循环。在开发铀-钍循环的初期,建议用铀-235代替铀-233作为核燃料。研究了在快中子反应堆中进行铀钍循环的微量锕系元素嬗变。已经考虑了这种反应堆堆芯结构的几种方案。已经证明,不均匀放置的镅比均匀放置的嬗变率更高。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
求助全文
约1分钟内获得全文 求助全文
来源期刊
CiteScore
0.40
自引率
0.00%
发文量
0
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
联系我们:info@booksci.cn Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。 Copyright © 2023 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信