液态金属冷却快堆子通道分析软件SACOS-LMR研发与工程应用OA北大核心CSTPCD

Against the backdrop of China's ambitious three-step nuclear energy develop-ment 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 character-istics 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 safe-ty analysis of the European Lead-cooled Fast Reactor(ALFRED)core was conducted.The calculated results are not only reasonable but also exhibit consistency with compara-ble 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.