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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of LOCA Blow-Down Transport for OPR-1000 Plant Jong Pil Park and Ji Hwan Jeong (PNU), Man Woong Kim (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of PASS Effectiveness Under Severe Accidents in Nuclear Power Plants Yu Jung CHOI, Sung Bok LEE, and Hyeong Taek KIM (KHNP), Jin Yong LEE (FNC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Water Hammer Mitigation on Postulated Pipe Break of Feed Water System Ho Je Seong, Kab Koo Woo, and Keon Taek Cho (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Transient Flow Field in Containment Floor Following a LOCA of APR-1400 Young Seok Bang, Gil-Soo Lee, Byung-Gil Huh, Deog-Yeon Oh, and Sweng Woong Woo (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Parametric Calculations for Subcooling and Triggering Timing Effects in a TROI Test I. K. Park, J. H. Kim, B. T. Min, and S. W. Hong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis of Square Flow Channel in Thermal Engine Rocket Adventurer for Space Nuclear Application S. H. Nam and K. Y. Suh (SNU), S. G. Kang (PHILOSOPHIA) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Performance Analysis Using CFD Code of the Reactor Coolant Pump for the APR1400 Ja Y. GU (PHILOSOPHIA), Kune Y. SUH (SNU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Analysis of Hydrogen Control Strategy Using Igniter During Severe Accident Sung Bok LEE and Hyeong Taek KIM (KHNP), Keo Hyoung LEE (FNC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Assessment of OPR1000 Design Load-Following Operation Capability on Large Load Reduction Joo-sung Kim, Yong-jin Cho, Man-woong Kim, and Seung-hoon Ahn (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Feasibility Study to Lower Steam Generator Low Water Level Trip Setpoint to Reduce Unnecessary Scram Frequency for KORI 3,4 Plant M. S. Jung, C. S. Lee, G. C. Lee, and E. K. Kim (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Study on Effect of the Crud Deposits During LBLOCA Condition Byung Gil Huh, Joosuk Lee, Young Seok Bang, Deog-Yeon Oh, and Sweng Woong Woo (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) SBLOCA Mass and Energy Release Analysis for UCN 3&4 T. M. Kim, C. W. Kim, H. R. Choi, and E. K. Kim (KOPEC) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) ECC Bypass Characteristics of a 4-EDG DVI System Tae-Soon Kwon (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Characteristics of an ECC Injection Type Tae-Soon Kwon and Chul-Hwa Song (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of the PRT Rupture Disk Flow During an Inadvertent Safety Injection Event at Kori Unit 3 Seung Wook Lee, Kyung Doo Kim, and Sung Won Bae (KAERI), Kang Cheol Jeong and Jong Bae Lee (KHNP) PDF보기 -
Last Modified : 1998-Autumn