Simulation of neutron diffusion and transient analysis of MSR

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

doi:10.13538/j.1001-8042/nst.25.020601

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Simulation of neutron diffusion and transient analysis of MSR

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-01-20

- Simulation of neutron diffusion and transient analysis of MSR
- Nuclear Science and Techniques Vol. 25, Issue 2, Article number: 020601(2014)
- Affiliations：
  
  1.School of Information Science and Technology, East China Normal University, Shanghai200241, China
  2.Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai201800, China
- Author bio：
  
  Corresponding author, ddhan@ee.ecnu.edu.cn
- Funds：
- DOI：10.13538/j.1001-8042/nst.25.020601
  CLC：
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Liang ZHU, Peng PU, Sha DU, et al. Simulation of neutron diffusion and transient analysis of MSR. [J]. Nuclear Science and Techniques 25(2):020601(2014)
DOI：

Liang ZHU, Peng PU, Sha DU, et al. Simulation of neutron diffusion and transient analysis of MSR. [J]. Nuclear Science and Techniques 25(2):020601(2014) DOI： 10.13538/j.1001-8042/nst.25.020601.

摘要

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.

关键词

Keywords

Molten salt reactorNeutron diffusionTransient analysisSimulation software

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Related Institution

University of Chinese Academy of Sciences

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