Burnup optimization of once-through molten salt reactors using enriched uranium and thorium  

作　　者：Meng-Lu Tan Gui-Feng Zhu Zheng-De Zhang Yang Zou Xiao-Han Yu Cheng-Gang Yu Ye Dai Rui Yan 

机构地区：[1]Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China [2]University of Chinese Academy of Sciences,Beijing 100049,China [3]Shanghai Jiao Tong University,Shanghai 200240,China

出　　处：《Nuclear Science and Techniques》2022年第1期44-59,共16页核技术（英文）

基　　金：supported by the Shanghai Sailing Program(No.19YF1457900);Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000);National Natural Science Foundation of China(No.12005290);Youth Innovation Promotion Association of the Chinese Academy of Sciences(No.2020261)。

摘　　要：The advantages of once-through molten salt reactors include readily available fuel,low nuclear proliferation risk,and low technical difficulty.It is potentially the most easily commercialized fuel cycle mode for molten salt reactors.However,there are some problems in the parameter selection of once-through molten salt reactors,and the relevant burnup optimization work requires further analysis.This study examined once-through graphitemoderated molten salt reactor using enriched uranium and thorium.The fuel volume fraction(VF),initial heavy nuclei concentration(HN_(0)),feeding uranium enrichment(E_(FU)),volume of the reactor core,and fuel type were changed to obtain the optimal conditions for burnup.We found an optimal region for VF and HN_(0) in each scheme,and the location and size of the optimal region changed with the degree of E_(FU),core volume,and fuel type.The recommended core schemes provide a reference for the core design of a once-through molten salt reactor.

关 键 词：Once-through fuel cycle Molten salt reactor Enriched uranium THORIUM 

分 类 号：TL426[核科学技术—核技术及应用]