Author:
Kim Ji Yong,Park Ye Yeong,Bang In Cheol
Funder
Ministry of Science, ICT and Future Planning
National Research Foundation of Korea
Korea Hydro and Nuclear Power
Subject
Nuclear Energy and Engineering
Reference44 articles.
1. Assessment of RELAP5 code model to simulate U-shaped heat pipe performance for heat sink, in;Antariksawan;J. Phys. Conf. Ser., IOP Publishing,2019
2. Integral Effect Test and MARS-KS Calculation with Uncertainty Propagation Analysis for Direct Vessel Injection Line Break Intermediate-Break Loss-of-Coolant Accident;Bae;Nucl. Technol.,2021
3. Assessment of passive safety system of a Small Modular Reactor (SMR);Butt;Ann. Nucl. Energy,2016
4. J. Choi, B. Woods, Evaluation of Advanced Thermal-Hydraulic System Codes for Safety Analysis of Integral Type PWR, in: ASME Int. Mech. Eng. Congr. Expo., American Society of Mechanical Engineers, 2013: p. V06BT07A046.
5. MARS-KS code validation activity through the atlas domestic standard problem, American Nuclear Society, 555 North Kensington Avenue, La Grange Park;Choi;IL …,2012
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