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为研究热管冷却双模式空间堆(HP-BSNR)堆芯稳态热工水力安全特性,基于改进后的双模式反应堆初步概念设计方案建立了其堆芯热工水力模型,包括推进模式和电源模式下的燃料元件单通道模型、换热模型、压降计算模型以及热管模型等,开发了堆芯稳态热工水力分析程序STHA_HPBSNR。采用文献的实验数据以及程序ELM的计算结果与程序STHA_HPBSNR的氢气物性计算模块和热力学参数计算模块进行对比,初步验证了程序STHA_HPBSNR用于双模式空间堆系统热力学稳态计算分析的可靠性。此外分析了不同换热关系式和摩擦阻力关系式对通道壁面温度的影响,为后续将STHA_HPBSNR程序应用于双模式空间堆堆芯瞬态安全分析奠定了基础。
In order to study the steady-state thermal-hydraulic safety characteristics of HP-BSNR core, a thermal-hydraulic model of reactor core was established based on the improved conceptual design of dual-mode reactor, including propulsion mode and power mode Under the single-channel fuel element model, heat transfer model, pressure drop calculation model and heat pipe model, developed a core steady state thermal hydraulic analysis program STHA_HPBSNR. The reliability of the program STHA_HPBSNR for the thermodynamic steady state calculation and analysis of the dual-mode space reactor system is preliminarily verified by using the experimental data from the literature and the calculation results of the program ELM and the hydrogen physicality calculation module and the thermodynamic parameter calculation module of the program STHA_HPBSNR. In addition, the influences of different heat transfer and frictional resistances on the temperature of channel walls were analyzed, which laid the foundation for the subsequent STHA_HPBSNR program to be applied to the transient safety analysis of dual-mode space reactor core.