摘要
固体核燃料与推进剂之间的换热设计是核热推进系统的核心技术.本文建立了核热推进冷却通道的传热模型,通过与公开文献对比,验证了数值仿真方法的准确性与可靠性,并分析了核热推进冷却通道几何参数、质量流量等参数对传热的影响。研究结果显示,工质质量流量增加会引起出口温度降低和入口压力增高;冷却通道直径增加会引起出口温度降低和吐口压力降低;六棱柱流道换热效果优于圆柱通道.
The heat transfer between solid nuclear fuel and propellant is the core technology of nuclear thermal propulsion system.This paper established a model of heat transfer in the cooling channel of nuclear thermal propulsion system and verified the accuracy and reliability of the model and numerical simulation by comparing with reference.The influence of the geometrical parameters of the channel and the mass flow on the heat transfer were analyzed.The results showed that the temperature at channel outlet reduce and the pressure at channel inlet rise with the increase of mass flow;the temperature at channel outlet and the pressure at channel inlet reduce with the increase of channel diameter;the heat transfer effect of hexagonal prism flow channel is better than that of circular channel.
作者
艾青
王帅
吴家欢
张昊春
夏新林
AI Qing;WANG Shuai;WU Jia-Huan;ZHANG Hao-Chun;XIA Xin-Lin(School of Energy Science and Engineering,Harbin Institute of Technology,Harbin 150001,China)
出处
《工程热物理学报》
EI
CAS
CSCD
北大核心
2018年第12期2745-2748,共4页
Journal of Engineering Thermophysics
基金
国家自然科学基金资助项目(No.51676055)
核反应堆系统设计技术重点实验室(No.SQ-KFKT-02-2016005)
关键词
核热推进
冷却通道
传热
数值模拟
nuclear heat propulsion
cooling channel
heat transfer
numerical simulation.
