RHEE Bo | Korea Atomic Energy Research Institute
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概要
関連著者
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Park Joo
Korea Kumho Petrochemical Co. Ltd. Chungnam Kor
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KIM Hyoung
Korea Research Institute of Chemical Technology
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Park Joo
Korea Atomic Energy Research Institute
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RHEE Bo
Korea Atomic Energy Research Institute
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Kim Hyoung
Korea Atomic Energy Research Institute
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Min Byung-Joo
Korea Atomic Energy Research Institute
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YOON Churl
Korea Atomic Energy Research Institute
著作論文
- Application of a Zircaloy/Steam Oxidation Model to a CFD Code and its Validation against a CANDU Fuel Channel Experiment : CS28-2
- Moderator Analysis of Wolsong Units 2/3/4 for the 35% Reactor Inlet Header Break with a Loss of Emergency Core Cooling Injection
- Benchmark Calculations of a Radiation Heat Transfer for a CANDU Fuel Channel Analysis using the CFD Code