Preliminary safety analysis for heavy water-moderated molten salt reactor  

作　　者：Gao-Ang Wen Jian-Hui Wu Chun-Yan Zou Xiang-Zhou Cai Jin-Gen Chen Man Bao 

机构地区：[1]College of Science,University of Shanghai for Science and Technology,Shanghai 200093,China [2]Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China [3]University of Chinese Academy of Sciences,Beijing 100049,China

出　　处：《Nuclear Science and Techniques》2024年第6期202-217,共16页核技术（英文）

基　　金：the National Natural Science Foundation of China(No.11905285);the Shanghai Natural Science Foundation(No.20ZR1468700);the Youth Innovation Promotion Association CAS(No.2022258).

摘　　要：The heavy water-moderated molten salt reactor(HWMSR)is a newly proposed reactor concept,in which heavy water is adopted as the moderator and molten salt dissolved with fissile and fertile elements is used as the fuel.Issues arising from graphite in traditional molten salt reactors,including the positive temperature coefficient and management of highly radio-active spent graphite waste,can be addressed using the HWMSR.Until now,research on the HWMSR has been centered on the core design and nuclear fuel cycle to explore the viability of the HWMSR and its advantages in fuel utilization.However,the core safety of the HWMSR has not been extensively studied.Therefore,we evaluate typical accidents in a small modular HWMSR,including fuel salt inlet temperature overcooling and overheating accidents,fuel salt inlet flow rate decrease,heavy water inlet temperature overcooling accidents,and heavy water inlet mass flow rate decrease accidents,based on a neutronics and thermal-hydraulics coupled code.The results demonstrated that the core maintained safety during the investigated accidents.

关 键 词：Heavy water-moderated molten salt reactor Neutronics and thermal-hydraulics coupling Transient analysis Accident analysis 

分 类 号：TL426[核科学技术—核技术及应用]