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熔盐堆(Molten Salt Reactor,MSR)是第四代反应堆6种堆型中唯一的液态燃料反应堆,与固态燃料-液体冷却剂反应堆相比,原理上有较大不同。在熔盐堆中,流动的熔盐既是燃料又是冷却剂与慢化剂,中子物理学与热工水力学相互耦合;由于熔盐的流动性,缓发中子先驱核会随燃料流至堆芯外衰变,造成缓发中子的丢失,导致堆芯反应性降低。正是由于熔盐堆的这些新特性,造成熔盐堆内缓发中子先驱核、温度等参数变化与固态燃料反应堆有所不同,需要研究熔盐堆在各种工况下的相关物理参数变化。本文主要工作是考虑缓发中子先驱核的流动性对熔盐堆的影响,研究适用于熔盐堆的二维圆柱几何时空中子动力学程序及与之耦合的热工水力学程序;利用该程序对熔盐堆中子物理学和热工水力学进行耦合计算,验证熔盐堆相关实验数据;并且计算了熔盐堆无保护启停泵及堆芯入口温度过冷过热工况,用于分析熔盐堆的安全特性。计算结果表明,程序能够对熔盐反应堆实验(Molten Salt Reactor Experiment,MSRE)的相关实验数据进行较好的模拟计算,并且验证了熔盐堆的固有安全性。
The Molten Salt Reactor (MSR) is the only liquid fuel reactor in the six reactor stacks of the fourth generation of reactors, which is fundamentally different in principle from the solid fuel-liquid coolant reactor. In the molten salt reactor, the flowing molten salt is both fuel and coolant and moderator, and the neutron physics and thermal hydraulics are coupled with each other. Due to the fluidity of the molten salt, the delayed neutron precursor nuclei will react with the fuel flow Decay to the outside of the core, resulting in the loss of delayed neutrons, resulting in reduced core reactivity. It is precisely because of these new features of the molten salt heap that the parameters of the delayed nucleation and temperature of the delayed neutron nuclei in the molten salt reactor are different from those of the solid-state fuel reactors. It is necessary to study the relevant physical parameters of the molten salt heaps under various working conditions Variety. The main work of this paper is to consider the impact of slowing the flow of neutron precursor nuclei on the molten salt reactor and to study the two-dimensional cylindrical geometry spatio-temporal neutron kinetics program and the coupled thermo-hydraulics program for molten salt reactor. The program is used to calculate the neutron physics and thermodynamics of molten salt reactor to verify the experimental data related to the molten salt reactor. The conditions of undercooling and overheating of the molten salt reactor unprotected start-stop pump and core inlet are calculated In analyzing the safety features of molten salt reactor. The calculation results show that the program can simulate the related experimental data of Molten Salt Reactor Experiment (MSRE) and verify the intrinsic safety of the molten salt reactor.