Nuclear Techniques ›› 2018, Vol. 41 ›› Issue (4): 40602-040602.doi: 10.11889/j.0253-3219.2018.hjs.41.040602

• NUCLEAR ENERGY SCIENCE AND ENGINEERING • Previous Articles     Next Articles

Analysis of decay heat in primary loop of molten salt reactor under normal conditions

ZHOU Bo1,2, YAN Rui1, ZOU Yang1, YANG Pu1, YU Shihe1, LIU Yafen1   

  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:2017-11-24 Revised:2018-01-05 Online:2018-04-10 Published:2018-04-11
  • Supported by:
    Supported by 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] The fissile nuclides in the molten salt reactor (MSR) will produce a large number of fission products under normal operation conditions, which would fill the entire primary loop system. The decay of the fission products would generate heat all the time, even though the fission power stopped. The accurate analysis of the decay heat has great significance on the safety analysis of the primary loop pipe and equipment. [Purpose] This study aims to establish a numerical model for analyzing the decay heat of the primary loop. [Methods] The numerical flow model of the decay heat was established for 2 MW MSR (Thorium Molten Salt Reactor-Liquid Fuel 1, TMSR-LF1) designed by Shanghai Institute of Applied Physics (SINAP), Chinese Academy of Sciences, and then solved by using Mathematica 7.0. The simulation results of the static burning of TMSR-LF1 of SINAP and molten salt reactor experiment (MSRE) of Oak Ridge National Laboratory, were compared with that of ORIGENS program, the deviations are within the range of ±4% and ±2.76% respectively. The decay heat distribution in primary pipe and equipments of the primary loop system under normal operating conditions of TMSR-LF1 was quantitatively analyzed to find the distribution rule of decay heat under different flow rates. [Results] The deviations of decay heat for TMSR-LF1 and MSRE, calculated by Mathematica and ORIGENS, are within the range of ±4% and ±2.76% respectively, under normal operating conditions. The decay heat accumulated rapidly in each region about 20 s after start-up of the reactor in full power and flow rate, and then began to rise slowly and tend to be an equilibrium value. After equilibrium, decay heat of core active area account for 46.7% of the total decay heat, and the upper plenum, the hot leg#1, the main pump, the hot leg#2, the heat exchanger, the cold leg and the lower plenum area accounted for 31.8%, 1.21%, 14.6%, 0.89%, 2.21%, 1.67% and 0.94% respectively. [Conclusion] The established analytical method and conclusions can provide important reference for thermal hydraulic safety analysis, residual removal system design, reactor power regulation and safety control.

Key words: Molten salt reactor, Primary loop system, Decay heat, Flow model

CLC Number: 

  • TL329