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高温、高流速氢气在圆管内流动换热特性研究
引用本文:房玉良,秦浩,王成龙,苏光辉,田文喜,秋穗正.高温、高流速氢气在圆管内流动换热特性研究[J].原子能科学技术,2020,54(10):1762-1770.
作者姓名:房玉良  秦浩  王成龙  苏光辉  田文喜  秋穗正
作者单位:西安交通大学 动力工程多相流国家重点实验室,核科学与技术学院,陕西 西安710049
摘    要:为探究工质在核热推进反应堆冷却剂通道内的热工水力行为,基于数值计算方法,开展了圆管内高温、高流速氢气流动换热特性研究。通过与实验数据对比发现,采用压力基耦合算法、SST k-ω湍流模型以及物性模型进行高温、高流速氢气流动换热特性数值模拟是合理可行的,计算值与实验值符合较好,计算模型选择正确。在分析基础工况流场与温度场的基础上,还研究了热工参数对氢气管内流动换热特性的影响,结果表明,随质量流量的增大换热效果增强,随热流密度的增大换热效果变差。研究方法与结果可为高温、高热流密度环境下气体工质流动换热特性研究、核热推进反应堆的热工设计与仿真模拟提供参考。

关 键 词:核热推进    氢气    内部流动换热    数值模拟    高温、高流速

Heat Transfer Performance of High Temperature and High Velocity Hydrogen Flow inside Circle Tube
FANG Yuliang,QIN Hao,WANG Chenglong,SU Guanghui,TIAN Wenxi,QIU Suizheng.Heat Transfer Performance of High Temperature and High Velocity Hydrogen Flow inside Circle Tube[J].Atomic Energy Science and Technology,2020,54(10):1762-1770.
Authors:FANG Yuliang  QIN Hao  WANG Chenglong  SU Guanghui  TIAN Wenxi  QIU Suizheng
Affiliation:State Key Laboratory of Multiphase Flow in Power Engineering, School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
Abstract:In order to investigate the thermo-hydraulic characteristics of working fluids in the coolant channel of nuclear thermal propulsion reactors, the flow and heat transfer performance of high temperature and high velocity hydrogen in the circle tube was studied by the numerical calculation method. Comparing with the experimental data, it is found that the pressure-based coupled algorithm, SST k-ω turbulence model and hydrogen property model are reasonable and feasible to simulate the flow and heat transfer performance of hydrogen at high temperature and high velocity. The calculated values agree well with the experimental data, and the numerical simulation model is correct. Based on the analysis of flow and temperature field of the base case, the effects of thermal parameters on the flow and heat transfer performance of hydrogen were also studied. The increasing inlet mass flow rate enhances heat transfer performance and the increasing heat flux weakens it. The methods and results can provide some references and guidance for the study of the flow and heat transfer performance of gaseous fluid under high temperature and high heat flux, and thermal design and simulation of nuclear thermal propulsion reactor.
Keywords:nuclear thermal propulsion                                                                                                                        hydrogen                                                                                                                        internal flow and heat transfer                                                                                                                        numerical simulation                                                                                                                        high temperature and high velocity
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