Nuclear Techniques ›› 2017, Vol. 40 ›› Issue (10): 100605-100605.doi: 10.11889/j.0253-3219.2017.hjs.40.100605

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Develop and verify coupling program of the neutron physics and thermal hydraulic for MSR

WEI Quan1,2, GUO Wei1, WANG Hailing1, CHEN Jingen1, CAI Xiangzhou1   

  1. 1. Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Jiading Campus, Shanghai 201800, China;
    2. University of Chinese Academy of Sciences, Beijing 100049, China
  • Received:2017-04-10 Revised:2017-05-12 Online:2017-10-10 Published:2017-09-29
  • Supported by:
    Supported by National Natural Science Foundation of China (No.91326201), Strategic Priority Research Program of Chinese Academy of Sciences (No.XDA02010000), the Frontier Science Key Program of Chinese Academy of Sciences (No.QYZDY-SSW-JSC016)

Abstract: Background: As one of the six candidates for the Generation IV reactor types, molten salt reactor (MSR) is characterized by its use of the fluid-fuel. Compared with solid-fuel reactors, there are some differences in physics for liquid fuel reactor. The fluid-fuel not only serves as the fuel, but also serves as both the coolant and the moderator, hence a must for the neutron physics coupling with the thermal-hydraulic. Due to fuel flow in MSR, the delayed neutron precursors (DNP) partly flow out and decay outside of the reactor core, resulting in reactivity losses in the core. Purpose: This study aims to develop and verify coupling program of neutron physics and thermal-hydraulic for MSR. Methods: Distribution of DNP and temperature is different from solid-fuel reactor, it is necessary to study the change of relevant physical parameters in MSR under different operating conditions. Considering the flow of DNP impacting on MSR, a new space-time neutron dynamics program was developed to couple with the thermal-hydraulics program on the basis of two-dimensional RZ cylindrical geometry. The unprotected pump driven transient and inlet fuel temperature overcooling/overheating transient was simulated to analyze the intrinsic safety of MSR. Results: The related experimental data in molten salt reactor experiment (MSRE) were verified by coupling calculation of neutron dynamics and thermal hydraulics, and the results showed that simulated data was in good agreement with the experiment results. Conclusion: The program is available in simulating related experimental data in MSRE, and MSR has intrinsic safety.

Key words: MSR, Delayed neutron precursors, Reactivity, Intrinsic safety

CLC Number: 

  • TL364