Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme

作     者：Xue-Chao Zhao Rui Yan Gui-Feng Zhu Ya-Fen Liu Jian Guo Xiang-Zhou Cai Yang Zou Xue-Chao Zhao;Rui Yan;Gui-Feng Zhu;Ya-Fen Liu;Jian Guo;Xiang-Zhou Cai;Yang Zou

作者机构：Shanghai Institute of Applied PhysicsChinese Academy of SciencesShanghai 201800China CAS Innovative Academies in TMSR Energy SystemChinese Academy of SciencesShanghai 201800China University of Chinese Academy of SciencesBeijing 100049China 

出 版 物：《Nuclear Science and Techniques》 (核技术（英文）)

年 卷 期：2024年第35卷第4期

页      面：15-28页

核心收录：

学科分类：082703[工学-核技术及应用] 08[工学] 0827[工学-核科学与技术] 

基　　金：supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000) Chinese Academy of Sciences Talent Introduction Youth Program(No.SINAP-YCJH-202303) Chinese Academy of Sciences Special Research Assistant Funding Project and Shanghai Pilot Program for Basic Research-Chinese Academy of Science,Shanghai Branch(JCYJ-SHFY-2021-003) 

主　　题：Molten salt fuel Plutonium utilization ^(233)U TRUs mole fraction Temperature feedback coefficient 

摘      要：A molten salt reactor(MSR)has outstanding features considering the application of thorium fuel,inherent safety,sustainability,and resistance to ***,fissile material^(233)U is significantly rare at the current stage,thus it is difficult for MSR to achieve a pure thorium-uranium fuel ***,using plutonium or enriched uranium as the initial fuel for MSR is more *** this study,we aim to verify the feasibility of a small modular MSR that utilizes plutonium as the starting fuel(SM-MSR-Pu),and highlight its advantages and ***,the structural design and fuel management scheme of the SM-MSR-Pu were ***,the neutronic characteristics,such as the graphite-irradiation lifetime,burn-up performance,and coefficient of temperature reactivity were calculated to analyze the physical characteristics of the *** results indicate that plutonium is a feasible and advantageous starting fuel for a SM-MSR;however,there are certain shortcomings that need to be *** a 250 MWth SM-MSR-Pu,approximately 288.64 kg^(233)U of plutonium with a purity of greater than 90% is produced while 978.00 kg is burned every ten *** temperature reactivity coefficient decreases from -4.0 to -6.5 pcm K^(-1) over the 50-year operating time,which ensures a long-term safe ***,the amount of plutonium and accumulation of minor actinides(MAs)would increase as the burn-up time increases,and the annual production and purity of^(233)U will *** achieve an optimal burn-up performance,setting the entire operation time to 30 years is ***,more than 3600 kg of plutonium eventually accumulate in the *** research is required to effectively utilize this accumulated plutonium.