摘要
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 core steady-state safety characteristics of Bimodal Space Nuclear Reactor with Heat Pipe（HP-BSNR）, the thermal-hydraulic models of modified core are established and a steady-state thermal-hydraulic analysis code for the HP-BSNR named STHA_HPBSNR is developed based on the preliminary conceptual design of HP-BSNR. The hydrogen property and steady-state thermal-hydraulic parameters calculated by STHA_HPBSNR are compared with that calculated by program ELM as well as the experimental data in the published literatures, which turn out to agree well. Besides, the effect of different heat transfer and friction resistance correlations on the channel wall temperature is studied. It demonstrates that the STHA_HPBSNR can provide the initial steady-state parameters for the transient-state safety analysis of HP-BSNR.
作者
田晓艳
江新标
陈立新
李华琪
杨宁
朱磊
马腾跃
Tian Xiaoyan Jiang Xinbiao Chen Lixin Li Huaqi Yang Ning Zhu Lei Ma Tengyue(State Key Laboratory of Intense Pulsed Radiation Simulation and Effect, Northwest Institute of Nuclear Technology, Xi＇an, 710024, China)
出处
《核动力工程》
EI
CAS
CSCD
北大核心
2017年第5期34-39,共6页
Nuclear Power Engineering
基金
基金项目:先进热管冷却空间快堆动态特性研究(11375143)
关键词
双模式空间堆
稳态
热工水力
程序开发
Bimodal Space Reactor, Steady-State, Thermal-Hydraulic, Code development
