Simulation of neutron diffusion and transient analysis of MSR  

作　　者：朱亮 蒲鹏 杜莎 韩定定 

机构地区：[1]School of Information Science and Technology,East China Normal University [2]Shanghai Institute of Applied Physics,Chinese Academy of Sciences

出　　处：《Nuclear Science and Techniques》2014年第2期89-94,共6页核技术（英文）

基　　金：Supported by the National Nature Science Foundation of China(Nos.11075057.11035009 and 10979074)

摘　　要：Molten salt reactor(MSR) is a potential nuclear power reactor of Generation Ⅳ.The working process of the primary loop of an MSR is studied in this paper.A physical model is established to describe the coupled heat transfer for the MSR core channels,the temperature negative feedback and the neutron characteristics.The simulation code,NDPID,has been developed with the object-oriented method,conducting the neutron diffusion and transient analysis in a parallel way.The simulation data and diagrams of neutron,power,flow rate and temperature can be obtained via graphical user interface.The simulation results can be used for further study on MSRs of larger dimensions and more complicated geometry.Molten salt reactor （MSR） is a potential nuclear power reactor of Generation IV. The working process of the primary loop of an MSR is studied in this paper. A physical model is established to describe the coupled heat transfer for the MSR core channels, the temperature negative feedback and the neutron characteristics. The simulation code, NDP1D, has been developed with the object-oriented method, conducting the neutron diffusion and transient analysis in a parallel way. The simulation data and diagrams of neutron, power, flow rate and temperature can be obtained via graphical user interface. The simulation results can be used for further study on MSRs of larger dimensions and more complicated geometry.

关 键 词：中子扩散 瞬态分析 MSR 模拟 图形用户界面 仿真数据 核电反应堆 模型描述 

分 类 号：TL426[核科学技术—核技术及应用]