摘要
为提高反应堆安全性,基于自然循环的非能动余热排出系统在小型反应堆中有着广泛的应用。本文基于已完成的小型一体化核动力装置中间回路换热实验,用RELAP5(Reactor Excursion and Leak Analysis Program)对中间回路自然循环运行特性开展了计算分析工作。研究发现,载热功率的程序计算结果与实验数据符合良好,可表征系统的自然循环特性。在余热排出系统中,系统回路的压力由蒸汽发生器(Steam Generator,SG)一次侧平均温度所决定,SG一次侧入口温度、质量流量与冷热源高度差对余热排出系统换热性能影响显著。当SG一次侧入口温度较高时,余热排出系统换热性能对系统回路阻力更加敏感,这些结果为进一步研究小型堆非能动系统提供了有价值的应用。
[Background]Passive residual heat-removal system(PRHRS)based on natural circulation has been widely used in small reactors connected on secondary side loop.[Purpose]This study aims to develop and analyze a passive residual heat-removal system on the secondary side of a small reactor to improve reactor safety.[Methods]Based on the completed heat-transfer experiment of the intermediate circuit of a small integrated nuclear power plant,Reactor Excursion and Leak Analysis Program(RELAP)was employed to determine and analyze the natural circulation characteristics of the intermediate loop were determined and analyzed.[Results]The heat transfer rate results of the program are in good agreement with the experimental data,and the natural cycle characteristics of PRHRS can be characterized.The pressure of the system loop is determined by the average temperature of the primary side of the steam generator(SG),and the difference in the inlet temperature of the SG primary side,mass flow rate,and height of the cooling and heating sources significantly influence the heat-transfer performance of the SG system.The heat-transfer performance of the waste-heat-removal system is more sensitive to the resistance of the system loop when the temperature of the primary-side inlet of the SG is higher.[Conclusions]These results provide a valuable application for further investigations of passive systems in small reactors.
作者
董博通
肖瑶
李俊龙
徐子伊
刘茂龙
刘利民
傅俊森
顾汉洋
DONG Botong;XIAO Yao;LI Junlong;XU Ziyi;LIU Maolong;LIU Limin;FU Junsen;GU Hanyang(College of Smart Energy,Shanghai Jiaotong University,Shanghai 200240,China;School of Mechanical Engineering,Shanghai Jiaotong University,Shanghai 200240,China)
出处
《核技术》
EI
CAS
CSCD
北大核心
2024年第3期109-115,共7页
Nuclear Techniques
基金
国家自然科学基金(No.12075150,No.12275174)资助。
