MW级空间核反应堆系统热管式辐射散热器分析及优化

张昊春; 刘秀婷; 魏前明; 游尔胜; 孙铭远

doi:10.7538/yzk.2020.youxian.0018

MW级空间核反应堆系统热管式辐射散热器分析及优化

哈尔滨工业大学能源科学与工程学院,黑龙江哈尔滨150001
中国核动力研究设计院中核核反应堆热工水力技术重点实验室,四川成都610213

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- 刊出日期: 2020-07-19

Analysis and Optimization of Heat Pipe Radiation Radiator for MW Space Nuclear Reactor System

School of Energy Science and Engineering, Harbin Institute of Technology,Harbin 150001, China
CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610213, China

摘要

摘要: 空间核反应堆是空间核电源和核推进的研究基础，大功率核反应堆的体积和质量一直是限制航空航天设计的重要因素。针对这一问题，本文对MW级空间核反应堆系统热管式辐射散热器进行建模和分析，建立热管式辐射散热器的热阻模型，利用穷举法和遗传算法在给定工况下探讨裸碳纤维翅片长度L_f和厚度δ_f、冷却剂质量流量m、辐射散热器入口温度T_f1对散热器质量M的影响。结果表明，当T_f1＝800 K、L_f＝5 cm、δ_f＝0.16 mm、m＝9 kg/s时，M达到最优，为906.593 kg，优化了0.63%的系统质量。
- 空间核反应堆 ,
- 热管式辐射散热器 ,
- 遗传算法 ,
- 质量优化
Abstract: Space nuclear reactor is the research foundation of space nuclear power and nuclear propulsion. The volume and mass of high-power nuclear reactor are always the important factors limiting the aerospace design. In view of this problem, the heat pipe radiation radiator of MW space nuclear reactor system was modeled and analyzed, and the thermal resistance model of the heat pipe radiation radiator was established in this study. The effect of the length L_fand thickness δ_fof the bare carbon fiber fin, the mass flow m of the coolant, the inlet temperature T_f1 of the radiation radiator on the mass M of the radiation radiator was discussed under the given conditions by the exhaustive method and genetic algorithm. The results show that when T_f1 is 800 K, L_fis 5 cm, δ_f is 0.16 mm, and m is 9 kg/s, M is the best. At this time, M is 906.593 kg, and 0.63% of the system mass is optimized.
- space nuclear reactor ,
- heat pipe radiation radiator ,
- genetic algorithm ,
- mass optimization

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MW级空间核反应堆系统热管式辐射散热器分析及优化

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Analysis and Optimization of Heat Pipe Radiation Radiator for MW Space Nuclear Reactor System

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