Dynamic analysis for a 2 MW liquid-fueled molten salt reactor

被引:9
作者
Cui, Y. [1 ,2 ,3 ]
Cui, L. [1 ,2 ,3 ]
Xia, S. P. [1 ,2 ,3 ]
Chen, J. G. [1 ,2 ,3 ]
Cai, X. Z. [1 ,2 ,3 ]
机构
[1] Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
[2] CAS Innovat Acad TMSR Energy Syst, Shanghai 201800, Peoples R China
[3] Univ Chinese Acad Sci, Beijing 101408, Peoples R China
基金
中国国家自然科学基金;
关键词
Molten salt reactor; Reactivity; Delayed neutron precursors; Dynamics; Inherent safety; DELAYED NEUTRON FRACTION; CYCLE; CODE;
D O I
10.1016/j.pnucene.2020.103381
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In a liquid-fueled molten salt reactor (MSR), the fuel salt acts as both fuel and coolant, and the fission energy is released into the fuel salt immediately. The delayed neutron precursors drift through the graphite channels in the core and the primary loop during operation. Therefore, the dynamics for a MSR is characterized by the strong interplay between the neutronics and thermal hydraulics, which is significantly different from that of a solid-fueled reactor, such as PWR. In this study, a dynamic analysis for a graphite moderated, fluoride based, liquid-fueled molten salt reactor with a power of 2 MWth (TMSR-LF) is carried out based on a coupled neutronics/thermal hydraulics code named TMSR-2D. The steady-state characteristics including the distributions of flow field, temperature and neutron fluxes, and effective delayed neutron fraction under different fuel flow rates, transients perturbed by fuel pump start-up and coast-down, overcooling and overheating of inlet fuel and reactivity insertion are simulated and analyzed. The numerical results indicate that the dynamic behavior of TMSR-LF is acceptable in the aspect of reactor safety. Furthermore, the dynamic analysis offers valuable information for future construction and operation of this experimental reactor.
引用
收藏
页数:13
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