Space nuclear reactor power(SNRP)using a gas-cooled reactor(GCR)and a closed Brayton cycle(CBC)is the ideal choice for future high-power space missions.To investigate the safety characteristics and develop the control...Space nuclear reactor power(SNRP)using a gas-cooled reactor(GCR)and a closed Brayton cycle(CBC)is the ideal choice for future high-power space missions.To investigate the safety characteristics and develop the control strategies for gas-cooled SNRP,transient models for GCR,energy conversion unit,pipes,heat exchangers,pump and heat pipe radiator are established and a system analysis code is developed in this paper.Then,analyses of several operation conditions are performed using this code.In full-power steady-state operation,the core hot spot of 1293 K occurs near the upper part of the core.If 0.4$reactivity is introduced into the core,the maximum temperature that the fuel can reach is 2059 K,which is 914 K lower than the fuel melting point.The system finally has the ability to achieve a new steady-state with a higher reactor power.When the GCR is shut down in an emergency,the residual heat of the reactor can be removed through the conduction of the core and radiation heat transfer.The results indicate that the designed GCR is inherently safe owing to its negative reactivity feedback and passive decay heat removal.This paper may provide valuable references for safety design and analysis of the gas-cooled SNRP coupled with CBC.展开更多
利用有限元方法对空间核反应堆电源系统(space power reactor systems,SPRS)中热管冷却反应堆燃料组件进行了稳态热分析。针对相邻燃料组件间的理想接触与非理想接触两种情况,评估了组件间的热接触状况、功率水平对其温度场分布的影响...利用有限元方法对空间核反应堆电源系统(space power reactor systems,SPRS)中热管冷却反应堆燃料组件进行了稳态热分析。针对相邻燃料组件间的理想接触与非理想接触两种情况,评估了组件间的热接触状况、功率水平对其温度场分布的影响。结果表明:相邻燃料组件间在理想接触情况下,温度最高点位于燃料棒中心,随着表面传热系数的减小,温度最高点逐渐偏离燃料棒中心位置,且最高温度随功率水平的增大而呈线性增大。展开更多
基金the National Natural Science Foundation of China(Grant No.U1967203)the National Key R&D Program of China(Grant No.2019YFB1901100)and China Postdoctoral Science Foundation(Grant No.2019M3737).
文摘Space nuclear reactor power(SNRP)using a gas-cooled reactor(GCR)and a closed Brayton cycle(CBC)is the ideal choice for future high-power space missions.To investigate the safety characteristics and develop the control strategies for gas-cooled SNRP,transient models for GCR,energy conversion unit,pipes,heat exchangers,pump and heat pipe radiator are established and a system analysis code is developed in this paper.Then,analyses of several operation conditions are performed using this code.In full-power steady-state operation,the core hot spot of 1293 K occurs near the upper part of the core.If 0.4$reactivity is introduced into the core,the maximum temperature that the fuel can reach is 2059 K,which is 914 K lower than the fuel melting point.The system finally has the ability to achieve a new steady-state with a higher reactor power.When the GCR is shut down in an emergency,the residual heat of the reactor can be removed through the conduction of the core and radiation heat transfer.The results indicate that the designed GCR is inherently safe owing to its negative reactivity feedback and passive decay heat removal.This paper may provide valuable references for safety design and analysis of the gas-cooled SNRP coupled with CBC.
文摘利用有限元方法对空间核反应堆电源系统(space power reactor systems,SPRS)中热管冷却反应堆燃料组件进行了稳态热分析。针对相邻燃料组件间的理想接触与非理想接触两种情况,评估了组件间的热接触状况、功率水平对其温度场分布的影响。结果表明:相邻燃料组件间在理想接触情况下,温度最高点位于燃料棒中心,随着表面传热系数的减小,温度最高点逐渐偏离燃料棒中心位置,且最高温度随功率水平的增大而呈线性增大。
