Effect of reprocessing on neutrons of a molten chloride salt fast reactor

Due to their unique features, such as the inherent safety, simplified fuel cycle, and continuous on-line reprocessing, molten salt reactors (MSRs) are regarded as one of the six reference reactors in the Generation IV International Forum (GEN-IV). Molten chloride salt fast reactors (MCFRs) are a typ...

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Published inNuclear science and techniques Vol. 34; no. 3; pp. 154 - 170
Main Authors He, Liao-Yuan, Cui, Yong, Chen, Liang, Xia, Shao-Peng, Hu, Lin-Yi, Zou, Yang, Yan, Rui
Format Journal Article
LanguageEnglish
Published Singapore Springer Nature Singapore 01.03.2023
Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China
CAS Innovative Academies in TMSR Energy System,Chinese Academy of Sciences,Shanghai 201800,China
University of Chinese Academy of Sciences,Beijing 100049,China%University of Manchester,Manchester M139PL,UK
CAS Innovative Academies in TMSR Energy System,Chinese Academy of Sciences,Shanghai 201800,China%Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China
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Summary:Due to their unique features, such as the inherent safety, simplified fuel cycle, and continuous on-line reprocessing, molten salt reactors (MSRs) are regarded as one of the six reference reactors in the Generation IV International Forum (GEN-IV). Molten chloride salt fast reactors (MCFRs) are a type of MSR. Compared to molten fluoride salt reactors (MFSRs), MCFRs have a higher solubility of heavy metal atoms, a harder neutron spectrum, lower accumulation of fission products (FPs), and better breeding and transmutation performance. Thus, MCFRs have been recognized as a type of MSR with great prospects for future development. However, as the most important feature for MSRs, the effect of different reprocessing modes on MCFRs must be researched in depth. As such, this study investigated the effect of different isotopes, especially FPs, on the neutronic performance of an MCFR, such as its breeding performance. Furthermore, the characteristics of the different reprocessing modes and MCFR rates were analyzed in terms of safety, radioactivity level, neutron economy, and breeding capacity. In the end, a reprocessing method suitable for MCFRs was determined through calculation and analysis, which provides a reference for the further research of MCFRs.
ISSN:1001-8042
2210-3147
DOI:10.1007/s41365-023-01186-3