Acknowledgement
This work was supported by Korea Institute of Energy Technology Evaluation and Planning (KETEP) grant funded by the Korea government (MOTIE) (20214000000780, Methodology Development of High-fidelity Computational Fluid Dynamics for next generation nuclear power) and (RS-2023-00243201, Global Talent Development project for Advanced SMR Core Computational Analysis Technology Development). This work was additionally supported by a National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIT) (No. 2021M2E2A2081062).
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