Study on dynamic characteristics of fission products in 2 MW molten salt reactor

作     者：Bo Zhou Xiao-Han Yu Yang Zou Pu Yang Shi-He Yu Ya-Fen Liu Xu-Zhong Kang Gui-Feng Zhu Rui Yan Bo Zhou;Xiao-Han Yu;Yang Zou;Pu Yang;Shi-He Yu;Ya-Fen Liu;Xu-Zhong Kang;Gui-Feng Zhu;Rui Yan

作者机构：Shanghai Institute of Applied PhysicsChinese Academy of SciencesShanghai 201800China University of Chinese Academy of SciencesBeijing 100049China 

出 版 物：《Nuclear Science and Techniques》 (核技术（英文）)

年 卷 期：2020年第31卷第2期

页      面：42-54页

核心收录：

学科分类：082703[工学-核技术及应用] 08[工学] 0827[工学-核科学与技术] 

基　　金：supported by the Chinese Academy of Sciences TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000) The Frontier Science Key Program of Chinese Academy of Sciences(No.QYZDY-SSW-JSC016) 

主　　题：Molten salt reactor Fission products Radioactive source term Primary loop system Flow model 

摘      要：In this study,a numerical flow model of the fission products(FPs)in the primary loop system of a molten salt reactor(MSR)was established and solved using Mathematica *** simulation results were compared with those of the ORIGEN-S program in the static burnup mode,and the deviation was found to be less than 10%,which indicates that the results are in good ***,the FPs distribution in the primary loop system under normal operating conditions of the 2 MW MSR was quantitatively *** addition,the distribution phenomenon of the FPs under different flow rate conditions was *** the end of life,the FPs activity in the core region(including active region,and upper and lower plenum regions)accounted for 77.3%,and that in the hot leg #1,main pump,hot leg #2,heat exchanger,and cold leg region accounted for 1.2%,16.15%,0.99%,2.5%,and 1.9%,respectively,of the total FPs in the primary loop under normal operating *** proportion of FPs in the core decreased with the increase in flow rate in the range of 2.24-22,400 cm^3 s^-*** established analytical method and conclusions of this study can provide an important basis for radiation safety design of the primary loop,radioactive source management design,thermal-hydraulic safety analysis,and radiochemical analysis of FPs of 2 MW MSRs.