摘要
反应堆热工系统分析程序是开展热工水力计算与安全评价的重要工具。为开发适用于氦氙气冷空间堆的热工系统分析程序,本文在RELAP5/MOD4.0程序中拓展了氦氙混合气体(He-Xe)物性计算模块,添加了适用于He-Xe的传热关系式,将拓展后程序计算值与实验值进行对比。结果表明:程序默认的Sutherlands定律用于He-Xe物性计算时将引入较大误差;Dittus-Bolter公式对He-Xe对流换热时的Nu预测偏高,将导致不保守的壁温计算结果。拓展后的程序对He-Xe压降和换热计算结果均与实验值吻合较好,验证了程序开发的正确性以及程序用于He-Xe流动换热计算的功能。本研究可为系统层面程序开发奠定基础。
Thermal-hydraulic transient analysis code for reactor system is an important tool for thermal-hydraulic calculation and safety evaluation.To develop the thermal-hydraulic analysis code for the helium-xenon(He-Xe)cooled space reactor,the He-Xe physical properties were expanded into RELAP5/MOD4.0 and the suitable heat transfer correlation for He-Xe was also added.The comparison of calculations by the modified code with the experimental data was conducted.The results show that the default Sutherlands law will introduce large error for the He-Xe physical properties calculation.Predictions of Nusselt number by Dittus-Bolter formula overestimate the experimental data for He-Xe flow and heat transfer,resulting in an unsafe numerical margin for the wall temperature.Calculations of both pressure drop and heat transfer coefficient by the expanded code agree well with the experimental data,verifying the correctness of code development and the feasibility for calculating He-Xe flow and heat transfer.This research can lay the foundation for the system-level code development.
作者
周彪
孙倩
孙俊
孙玉良
ZHOU Biao;SUN Qian;SUN Jun;SUN Yuliang(Institute of Nuclear and New Energy Technology,Key Laboratory of Advanced Reactor Engineering and Safety of Ministry of Education,Tsinghua University,Beijing 100084,China)
出处
《原子能科学技术》
EI
CAS
CSCD
北大核心
2021年第11期1959-1966,共8页
Atomic Energy Science and Technology
基金
国家重点研发计划(2018YFB1900501)
民用航天项目(D010501)。
