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Preliminary Test of Passive Decay Heat Removal System: Insights and Future Directions

This study explores the preliminary testing of a passive decay heat removal system pivotal for nuclear reactor safety. Conducted by researchers In-Guk Kim and In Cheol Bang from UNIST, the experiment evaluates the performance of heat pipes in preventing reactor meltdown. The MARS simulation demonstrates the system's efficacy and potential improvements. Key results, discussions, and future work are presented, highlighting advancements in nuclear thermal hydraulics and safety measures essential for students and young researchers.

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Preliminary Test of Passive Decay Heat Removal System: Insights and Future Directions

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  1. Preliminary test of passive decay heat removal system In-GukKim, In Cheol Bang* School of Mechanical and Nuclear Engineering Ulsan National Institute of Science and Technology (UNIST) 50 UNIST-gil, Ulju-gun, Ulsan 689-798, Republic of Korea 5th Korea – Japan Joint Seminar on Nuclear Thermal Hydraulics and Safety for Students and Young Researchers Introduction Experiment • SAMPLE • SAMPLE Ga • SAMPLE Advantages O • SAMPLE Results and Discussion • SAMPLE Ultimate Goal • SAMPLE MARS Simulation • SAMPLE. Conclusions and Further work • SAMPLE. References Mochizuki, M. et al. (2013). “Prevention Possibility of Nuclear Power Reactor Meltdown by use of Heat Pipes for Passive Cooling of Spent Fuel,” Frontiers in Heat Pipes, 4, pp.013001. Wang, C. et al. (2013). “Study on the characteristics of the sodium heat pipe in passive residual heat removal system of molten salt reactor,” Nucl. Eng. Design., 265, pp.691-700. Wong, S. C. et al. (2008). “Visualization and Performance Measurement of Operating Mesh Wicked Heat Pipes,” Int. J. Heat Mass Transfer, 51, pp.4249-4259.

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