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Performance analysis of indirect contact heat pipe radiator for space nuclear power system

  • Zengen Li
  • , Haochun Zhang*
  • , Shuting Zhao
  • , Cheng Zhang
  • , Yan Xia
  • *Corresponding author for this work
  • School of Energy Science and Engineering, Harbin Institute of Technology
  • China Aerospace Science and Technology Corporation

Research output: Contribution to journalArticlepeer-review

Abstract

The heat pipe radiator, with excellent thermal conductivity and anti-collision performance, is expected very suitable for heat emission in nuclear-power spacecraft. Indirect contact heat pipe radiator could operate longer life with lower capital cost. In this paper, the fluid-solid coupling heat transfer method is integrated to solve the energy model and S–S radiation model based on the k-epsilon model. Optimization objectives, heat dissipation performance and temperature uniformity are adopted to optimize the radiator structure. A comparison analysis between the ordinary and optimized radiator is conducted based on energy and entropy variation. The results show that the temperature uniformity and heat dissipation characteristic of the radiator after the optimization of connection mode of heat pipe and coolant pipe, fin shape, and fins welding direction have been improved without changing the area of fins and the weight of radiator. Through the comparative of radiators after changing the working conditions, some useful conclusions are drawn, which provide the theoretical foundation for the experimental research and engineering practice.

Original languageEnglish
Article number105201
JournalProgress in Nuclear Energy
Volume172
DOIs
StatePublished - Jul 2024
Externally publishedYes

Keywords

  • Fluid-solid coupling heat transfer method
  • Heat pipe radiator
  • Simulation analysis
  • Space nuclear power

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