Neutronics analysis for MSR cell with different fuel salt channel geometries

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

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：2021年第32卷第1期

页      面：75-84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：This work was supported by the Chinese TMSR Strategic Pioneer Science and Technology Project(No.XDA02010000) the Frontier Science Key Program of Chinese Academy of Sciences(No.QYZDYSSW-JSC016) the Shanghai Sailing Program(No.Y931021031) 

主　　题：Molten salt reactor Fuel salt channel Cell geometry Neutronics 

摘      要：The neutronic properties of molten salt reactors(MSRs)differ from those of traditional solid fuel reactors owing to their nuclear fuel *** on the Monte-Carlo N particle transport code,the effects of the size and shape of the fuel salt channel on the neutron physics of an MSR cell are investigated systematically in this *** results show that the infinite multiplication factor(k?)first increases and then decreases with the change in the graphite cell size under certain fuel volume fraction(FVF)*** the same FVF and average chord length,when the average chord length is relatively small,the k?values for different fuel salt channel shapes agree *** the average chord length is relatively large,the k?values for different fuel salt channel shapes differ *** addition,some examples of practical applications of this study are presented,including cell selection for the core and thermal expansion displacement analysis of the cell.