摘要
液体燃料熔盐堆是第四代先进核能系统的候选堆型之一,应急排盐冷却系统是其可设置的特殊安全设计。本文以熔盐实验堆(Molten Salt Reactor Experiment,MSRE)应急排盐冷却系统为研究对象,探究换热元件内层屏障破损对其正常余热导出功能的影响。该研究基于计算流体动力学(Computational Fluid Dynamics,CFD)模拟方法,通过构建传热和多相流动模型分析破损后的传热和流动现象,并对关键影响参数进行敏感性分析。结果表明,内层套管破损后,18.4%的冷却水从破损位置经气隙层流出,单根换热元件功率提升到29.434 kW,破损位置附近外层套管出现局部温度低点。敏感性分析结果表明,破损尺寸、破损位置和气隙层压力变化均会对换热元件传热产生明显影响,其中传热对破损尺寸的敏感性最强。该分析结果可以为熔盐堆应急排盐冷却系统工程设计提供研究数据。
[Background]The liquid-fueled molten salt reactor(MSR)is one of the candidates for the Generation IV reactor technologies,and the fuel drain system is a special safety design.[Purpose]This study aims to investigate the influence of inner barrier leak of one heat exchange element of MSR on heat transfer characteristics.[Methods]Firstly,the fuel drain system of Molten Salt Reactor Experiment(MSRE)was taken as the research object,and computational fluid dynamics(CFD)simulation methods were employed to construct heat transfer and multiphase flow models to analyze the heat transfer and flow phenomena under normal operation and bayonet tube leak scenario.Then,the sensitivity analyses of key influencing parameters,such as the leak size(3~8 mm),leak location(10~1500 mm above the lower end of the heat exchange element)and pressure in the annular gas space(ranging from-13788 Pa to 13788 Pa),were carried out.[Results]The analysis results show that 18.4%of cooling water flows out from the leak location through the annular gas space when bayonet tube leak occurs and the power of one single heat exchange element increases to 29.434 kW.In addition,the lowest abnormal temperature appears in the thimble near the leak location.The sensitivity analysis results present that the heat transfer varies with the leak size,leak location and pressure of annular gas space and is most sensitive to leak size.[Conclusions]These analysis results of this study are valuable to the engineering design of the fuel drain system for MSRs.
作者
孙亮洁
梁荣健
蒋文涛
王超群
杨群
何兆忠
邹杨
SUN Liangjie;LIANG Rongjian;JIANG Wentao;WANG Chaoqun;YANG Qun;HE Zhaozhong;ZOU Yang(Shanghai Institute of Applied Physics,Chinese Academy of Sciences,Shanghai 201800,China;University of Chinese Academy of Sciences,Beijing 100049,China)
出处
《核技术》
北大核心
2026年第2期154-165,共12页
Nuclear Techniques
基金
中国科学院青年创新促进会项目(No.E3292901)
上海市"基础研究特区计划"(No.JCYJ-SHFY-2021-003)资助。
