Analysis of fast neutron flux rebound and burnup under once-through fuel cycle mode in a continuous zoning molten salt reactor

Nuclear Engineering and Design 2026 Open access

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Authors: Shuyang Jia, Guifeng Zhu, Zhenghao Xu, Changqing Yu, Yang Zou, Hongjie Xu
DOI: 10.1016/j.nucengdes.2026.114874
Cited by: 0
References: 36

Fields of Study & Subjects

Nuclear reactor physics and engineering Graphite nuclear technology radiation studies Nuclear Materials and Properties

Publication details

Journal / source
Nuclear Engineering and Design
Volume
452
Pages
114874–114874
Publication date
11 March 2026
Language
EN