Space nuclear power system is the key technology for deep space exploration missions in the future, especially for space base building-up. This paper evaluates several typical latest space nuclear reactor system （SNR...Space nuclear power system is the key technology for deep space exploration missions in the future, especially for space base building-up. This paper evaluates several typical latest space nuclear reactor system （SNRS） designs, and finds that most of their weights are heavier than necessary. From the point of weight-control, the SA4 design is the best but its design is more complex than others. A newly designed SNRS, based on the SAFE400 model, uses annular fuel and has better performance, with a fuel mass lower than that of the SAFE400 prototype by 18.75%. Meanwhile, different from former opinions, the delay neutron fractions of SNRS are not constant and change with the different SNRS designs. Therefore, designs of SNRS not to count the delayed neutron fracture or directly to consider it as 0.00677 are not appropriate.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
文摘Space nuclear power system is the key technology for deep space exploration missions in the future, especially for space base building-up. This paper evaluates several typical latest space nuclear reactor system （SNRS） designs, and finds that most of their weights are heavier than necessary. From the point of weight-control, the SA4 design is the best but its design is more complex than others. A newly designed SNRS, based on the SAFE400 model, uses annular fuel and has better performance, with a fuel mass lower than that of the SAFE400 prototype by 18.75%. Meanwhile, different from former opinions, the delay neutron fractions of SNRS are not constant and change with the different SNRS designs. Therefore, designs of SNRS not to count the delayed neutron fracture or directly to consider it as 0.00677 are not appropriate.
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。
