Differing from traditional pressurized water reactors(PWRs),heat pipe cooled reactors have the unique characteristics of fuel thermal expansion,expansion reactivity feedback,and thermal contact conductance.These react...Differing from traditional pressurized water reactors(PWRs),heat pipe cooled reactors have the unique characteristics of fuel thermal expansion,expansion reactivity feedback,and thermal contact conductance.These reactors require a new multiphysics coupling method.In this paper,a transient coupling method based on OpenFOAM is proposed.The method considers power variation,thermal expansion,heat pipe operation,thermal contact conductance,and gap conductance.In particular,the reactivity feedback caused by working medium redistribution in a heat pipe is also preliminarily considered.A typical heat pipe cooled reactor KRUSTY(Kilowatt Reactor Using Stirling TechnologY)is chosen as the research object.Compared with experimental results of load following,the calculated results are in good agreement and show the validity of the proposed method.To discuss the self-adjusting capability of this type of reactor system,a hypothetical accident is simulated.It is assumed that at the beginning of this accident,loss of the heat sink occurs.After 1500 s of the transient process,the reactor system recovers immediately.During this hypothetical accident,the control rod is always out of the reactor core,and the reactor only relies on the reactivity feedback to regulate the fission power.According to the simulation,the peak temperature is only about 1112 K,which is far below the safety limit.As for system recovery,the reactor needs approximately 2500 s to return to a steady state and can realize effective power regulation by reactivity feedback.This study confirms the availability of this coupling method and that it can be an effective tool for the simulation of heat pipe cooled reactors.展开更多
在我国核电技术自主化发展过程中,堆本体、燃料组件和蒸发器等主要设备的关键材料自主化是一个重要的基础问题。对于高温气冷堆(high temperature gas-cooled reactor,HTGR),这些关键材料主要涵盖核燃料、高温金属、核石墨、压力容器材...在我国核电技术自主化发展过程中,堆本体、燃料组件和蒸发器等主要设备的关键材料自主化是一个重要的基础问题。对于高温气冷堆(high temperature gas-cooled reactor,HTGR),这些关键材料主要涵盖核燃料、高温金属、核石墨、压力容器材料、高温气冷堆制氢相关材料等。受国内材料研发和制造水平所限,高温气冷堆部分关键材料仍采用国外进口材料。该文针对我国高温气冷堆核能技术所需的关键材料技术开展战略研究,研究关键材料的内容和范围、制造产业链、表征和应用等,提出对高温堆技术发展具有支撑性作用的关键材料体系及其工程化技术,并给出技术发展规划和建议。展开更多
基金supported by the National Key Research and Development Project of China(Grant No.2020YFB1901700)Science Challenge Project(Grant No.TZ2018001)+1 种基金the National Natural Science Foundation of China(Grant Nos.11775126 and 11775127)the Tsinghua University Initiative Scientific Research Program。
文摘Differing from traditional pressurized water reactors(PWRs),heat pipe cooled reactors have the unique characteristics of fuel thermal expansion,expansion reactivity feedback,and thermal contact conductance.These reactors require a new multiphysics coupling method.In this paper,a transient coupling method based on OpenFOAM is proposed.The method considers power variation,thermal expansion,heat pipe operation,thermal contact conductance,and gap conductance.In particular,the reactivity feedback caused by working medium redistribution in a heat pipe is also preliminarily considered.A typical heat pipe cooled reactor KRUSTY(Kilowatt Reactor Using Stirling TechnologY)is chosen as the research object.Compared with experimental results of load following,the calculated results are in good agreement and show the validity of the proposed method.To discuss the self-adjusting capability of this type of reactor system,a hypothetical accident is simulated.It is assumed that at the beginning of this accident,loss of the heat sink occurs.After 1500 s of the transient process,the reactor system recovers immediately.During this hypothetical accident,the control rod is always out of the reactor core,and the reactor only relies on the reactivity feedback to regulate the fission power.According to the simulation,the peak temperature is only about 1112 K,which is far below the safety limit.As for system recovery,the reactor needs approximately 2500 s to return to a steady state and can realize effective power regulation by reactivity feedback.This study confirms the availability of this coupling method and that it can be an effective tool for the simulation of heat pipe cooled reactors.
文摘在我国核电技术自主化发展过程中,堆本体、燃料组件和蒸发器等主要设备的关键材料自主化是一个重要的基础问题。对于高温气冷堆(high temperature gas-cooled reactor,HTGR),这些关键材料主要涵盖核燃料、高温金属、核石墨、压力容器材料、高温气冷堆制氢相关材料等。受国内材料研发和制造水平所限,高温气冷堆部分关键材料仍采用国外进口材料。该文针对我国高温气冷堆核能技术所需的关键材料技术开展战略研究,研究关键材料的内容和范围、制造产业链、表征和应用等,提出对高温堆技术发展具有支撑性作用的关键材料体系及其工程化技术,并给出技术发展规划和建议。
