Simulation of radiation dose distribution and thermal analysis for the bulk shielding of an optimized molten salt reactor  

作　　者：张志宏 夏晓彬 蔡军 王建华 李长园 葛良全 张庆贤 

机构地区：[1]Shanghai Institute of Applied Physics Chinese Academy of Sciences [2]University of Chinese Academy of Sciences [3]Chengdu University of Technology

出　　处：《Nuclear Science and Techniques》2015年第4期109-114,共6页核技术（英文）

基　　金：Supported by the"Strategic Priority Research Program"of the Chinese Academy of Sciences(No.XD02005002)

摘　　要：The Chinese Academy of Science has launched a thorium-based molten-salt reactor(TMSR)research project with a mission to research and develop a fission energy system of the fourth generation.The TMSR project intends to construct a liquid fuel molten-salt reactor(TMSR-LF),which uses fluoride salt as both the fuel and coolant,and a solid fuel molten-salt reactor(TMSR-SF),which uses fluoride salt as coolant and TRISO fuel.An optimized 2 MWth TMSR-LF has been designed to solve major technological challenges in the Th-U fuel cycle.Preliminary conceptual shielding design has also been performed to develop bulk shielding.In this study,the radiation dose and temperature distribution of the shielding bulk due to the core were simulated and analyzed by performing Monte Carlo simulations and computational fluid dynamics(CFD)analysis.The MCNP calculated dose rate and neutron and gamma spectra indicate that the total dose rate due to the core at the external surface of the concrete wall was 1.91μSv/h in the radial direction,1.16μSv/h above and 1.33μSv/h below the bulk shielding.All the radiation dose rates due to the core were below the design criteria.Thermal analysis results show that the temperature at the outermost surface of the bulk shielding was 333.86 K,which was below the required limit value.The results indicate that the designed bulk shielding satisfies the radiation shielding requirements for the 2 MWth TMSR-LF.The Chinese Academy of Science has launched a thorium-based molten-salt reactor （TMSR） research project with a mission to research and develop a fission energy system of the fourth generation. The TMSR project intends to construct a liquid fuel molten-salt reactor （TMSR-LF）, which uses fluoride salt as both the fuel and coolant, and a solid fuel molten-salt reactor （TMSR-SF）, which uses fluoride salt as coolant and TRISO fuel. An optimized 2 MWth TMSR-LF has been designed to solve major technological challenges in the Th-U fuel cycle. Preliminary conceptual shielding design has also been performed to develop bulk shielding. In this study, the radiation dose and temperature distribution of the shielding bulk due to the core were simulated and analyzed by performing Monte Carlo simulations and computational fluid dynamics （CFD） analysis. The MCNP calculated dose rate and neutron and gamma spectra indicate that the total dose rate due to the core at the external surface of the concrete wall was 1.91 μSv/h in the radial direction, 1.16 μSv/h above and 1.33 μSv/h below the bulk shielding. All the radiation dose rates due to the core were below the design criteria. Thermal analysis results show that the temperature at the outermost surface of the bulk shielding was 333.86 K, which was below the required limit value. The results indicate that the designed bulk shielding satisfies the radiation shielding requirements for the 2 MWth TMSR-LE

关 键 词：蒙特卡罗模拟 辐射剂量分布 熔盐堆 热分析 优化 计算流体力学 辐射剂量率 计算流体动力学 

分 类 号：TL426[核科学技术—核技术及应用]