Thermal-hydraulic and Safety Analysis of Space Hundred-kilowatt Lithium-cooled Fast Reactor

被引：0

作者：

Jin, Zhao ^{[1
]}

Wang, Chenglong ^{[1
]}

Liu, Xiao ^{[1
]}

Dai, Zhiwen ^{[1
]}

Tian, Wenxi ^{[1
]}

Qiu, Suizheng ^{[1
]}

Su, Guanghui ^{[1
]}

机构：

[1] School of Nuclear Science and Technology, Xi'an Jiaotong University, Xi'an,710049, China

来源：

Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2022年 / 56卷 / 03期

关键词：

Fast reactors - Codes (symbols) - Interplanetary flight - Space research - Transient analysis;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

As the increase of deep space exploration requirements, space high-power level nuclear reactor system is imperative. In this paper, for the space lithium-cooled fast reactor combined with the Stirling cycle, the models of core, Stirling generator, radiation radiator, pump and related pipeline were established. A system thermal-hydraulic analysis code was developed based on the Fortran language. The fidelity of the Stirling model was verified by the experimental data with the maximum relative error of 17.3%. The space lithium-cooled power system model was established. The system code was verified by comparing the steady-state calculated value with the design value with the maximum relative error of 13.3%. The transient analysis of the typical reactor accident was analyzed. The results show that the system has good safety performance due to the negative reactivity feedback of the core and the peak fuel temperature is within the safety limit. This paper provides theoretical support for the thermal-hydraulic and safety analysis of the hundred-kilowatt space reactor. © 2022, Editorial Board of Atomic Energy Science and Technology. All right reserved.

引用

页码：443 / 449