Preliminary proliferation study of the molten salt fast reactor

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2020-01-01 DOI:10.1051/epjn/2019062
M. Allibert, E. Merle, S. Delpech, D. Gérardin, D. Heuer, A. Laureau, S. Moreau
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引用次数: 1

Abstract

The molten salt reactor designs, where fissile and fertile materials are dissolved in molten salts, under consideration in the framework of the Generation IV International Forum, present some unusual characteristics in terms of design, operation, safety and also proliferation resistance issues. This paper has the main objective of presenting some proliferation challenges for the reference version of the Molten Salt Fast Reactor (MSFR), a large power reactor based on the thorium fuel cycle. Preliminary studies of proliferation resistance are presented here, dedicated to the threat of nuclear material diversion in the MSFR, considering both the reactor system itself and the processing units located onsite.
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熔盐快堆增殖初步研究
在第四代国际论坛框架内审议的熔盐反应堆设计,在设计、操作、安全和防扩散问题方面呈现出一些不同寻常的特点。熔盐反应堆将可裂变和可再生材料溶解在熔盐中。本文的主要目的是介绍参考版熔盐快堆(MSFR)的一些扩散挑战,这是一种基于钍燃料循环的大功率反应堆。这里介绍了抗扩散的初步研究,专门研究了MSFR中核材料转移的威胁,同时考虑了反应堆系统本身和现场的处理单元。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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