Nuclear Science and Techniques

《核技术》(英文版) ISSN 1001-8042 CN 31-1559/TL     2019 Impact factor 1.556

Nuclear Science and Techniques ›› 2014, Vol. 25 ›› Issue (2): 020601 doi: 10.13538/j.1001-8042/nst.25.020601

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Simulation of neutron diffusion and transient analysis of MSR

ZHU Liang, PU Peng, DU Sha, HAN Ding-Ding   

  1. 1School of Information Science and Technology, East China Normal University, Shanghai 200241, China
    2Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
  • Contact: HAN Ding-Ding E-mail:ddhan@ee.ecnu.edu.cn
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ZHU Liang, PU Peng, DU Sha, HAN Ding-Ding. Simulation of neutron diffusion and transient analysis of MSR.Nuclear Science and Techniques, 2014, 25(2): 020601     doi: 10.13538/j.1001-8042/nst.25.020601

Abstract:

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.

Key words: Molten salt reactor, Neutron diffusion, Transient analysis, Simulation software