液态金属冷却快堆子通道分析软件SACOS-LMR研发与工程应用  

Development and Application of Liquid Metal Cooled Fast Reactor Sub-channel Analysis Code SACOS-LMR

作　　者：王金顺 陈荣华[1] 朱昕阳 田家豪 田文喜[1] 秋穗正[1] 苏光辉[1] WANG Jinshun;CHEN Ronghua;ZHU Xinyang;TIAN Jiahao;TIAN Wenxi;QIU Suizheng;SU Guanghui(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049

出　　处：《原子能科学技术》2024年第3期581-592,共12页Atomic Energy Science and Technology

基　　金：国家自然科学基金(12275205)。

摘　　要：子通道分析方法是反应堆堆芯设计和热工水力分析的重要手段之一,对于我国提出的压水堆-快堆-聚变堆三步走核能发展战略,开发适用于液态金属冷却快堆热工安全分析的子通道分析程序具有重要意义。本文基于西安交通大学热工水力研究室自主开发的压水堆子通道程序SACOS,通过添加液态金属快堆特有的模型,如绕丝模型、盒间流模型、液态金属对流换热模型等,扩展至适用于液态金属快堆的子通道分析程序SACOS-LMR,该程序具备对液态金属快堆组件开展稳态和瞬态热工水力分析的功能。结合卡尔斯鲁厄开展的37棒钠冷瞬态实验,完成了SACOS-LMR程序的瞬态功能验证。基于验证后的SACOS-LMR程序,对欧洲铅冷快堆(ALFRED)堆芯开展了稳态工况和瞬态事故工况下的热工安全特性分析,计算结果合理,且与同类程序保持一致,表明SACOS-LMR程序可用于液态金属快堆的堆芯设计和热工水力分析研究。Against the backdrop of China’s ambitious three-step nuclear energy development strategy,encompassing pressurized water reactors(PWR),fast reactors(FR),and fusion reactors(FNR),the purpose of this study is to meet the pivotal need for a specialized sub-channel analysis code tailored to the unique thermal-hydraulic characteristics of liquid metal fast reactors(LMFRs).Building upon the foundational SACOS sub-channel code,the approach involves the seamless integration of LMFR-specific models.These include the wire-wrapped model,turbulent crossflow model,and liquid metal convective heat exchange model.The utilization of advanced computational techniques,such as the SIMPLE algorithm and staggered grid methodology,ensures the completion of accurate sub-channel calculations,establishing SACOS-LMR as a robust code for thermal-hydraulic safety analysis in LMFRs.Validation of the SACOS-LMR code was conducted through a sodium transient experiment involving 37-pin bundles at the Karlsruhe Institute of Technology.The results not only demonstrate a commendable alignment between computed parameters(e.g.temperature distribution,pressure drop)and experimental values but also confirm the code’s precision in transient analysis for LMFRs.Applying the validated SACOS-LMR code,an in-depth thermal-hydraulic safety analysis of the European Lead-cooled Fast Reactor(ALFRED)core was conducted.The calculated results are not only reasonable but also exhibit consistency with comparable codes,affirming SACOS-LMR’s applicability for LMFR core design and thermal-hydraulic analysis.In conclusion,this research represents a significant step forward in the development of LMFR technology.SACOS-LMR,with its validated capability in both steady-state and transient analysis,stands as a sophisticated and reliable sub-channel analysis tool.It not only supports LMFR core design but also contributes to the broader global pursuit of sustainable and clean energy solutions in the nuclear energy landscape.

关 键 词：液态金属冷却快堆 堆芯热工水力分析 子通道分析方法 ALFRED 

分 类 号：TL334[核科学技术—核技术及应用]