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To validate the heat transfer characteristics and pressure drop behavior in a core assembly. Learn more Search for specific researchers associated with
Analysis of maximum cladding temperature and margin to departure from nucleate boiling (DNB). 4. Conclusion
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This report presents a comprehensive numerical simulation and experimental validation of thermal-hydraulic behavior within high-temperature reactor designs, specifically focusing on the SC23667 project specifications. Using computational fluid dynamics (CFD) and system-level codes (e.g., DAYU3D ), we analyze safety margins, coolant flow distribution, and heat transfer efficiency under transient conditions. 1. Introduction