-->

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development and Assessment of SPACE Critical Flow Model TaeBeom Lee, ChangHwan Ban, JaeHoon Jeong, and SunTack Hwang(KEPCO NF) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Independent Verification of Effects of Spacer Grids during Reflood Phase for Implementation into SPACE Code YongMi Jung and Kyung Doo Kim(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Assessment of SG U-tubes Integrity during a Postulated Loss of All Heat Sinks in Wolsong NPPs by the CATHENA Code Hyoung Tae Kim, Dong Ha Kim, and Jin Hee Park(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) MAAP4 Analysis for Determining Rapidly Depressurization Valve Size Tae-Young Shin and Baek-Soon Chung(KEPCO RI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CHF Experiments under Realistic Severe Accident Condition for IVR-ERVC Strategy Tae Il Kim, Hae Min Park, and Soon Heung Chang(KAIST) Sun Heo(KHNP) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Analysis of Natural Circulation Flow in the Reactor Cavity under IVR-ERVC for SMART Rae-Joon Park, Sang-Baik Kim, and Youngho Jin(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Void Fraction Measurement at Premixing Stage in the TROI S.W. Hong, S.H. Hong, J.H. Kim, and K.S. Ha(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Steady State Calculation for SMART with MIDAS/SMR Jong-Hwa Park, Dong-Ha Kim, Young-Jong Chung, and Sunhee Park(KAERI) Song-Won Cho(KORTIC) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Study on the Steady State Layer Inversion of Melt Pool during Severe Accidents Kyoung-Ho Kang, Rae-Joon Park, Hee-Dong Kim, and Seong-Wan Hong(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of the Phenomenological Uncertainty Analysis Methodology Using MELCOR Code for the Containment Failure Probability of Level 2 PSA Suwon Lee and Gunhyo Jung(FNC Tech.) Kwngil Ahn and Sooyoung Park(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Simple Scheme for Prediction of Flame Acceleration and DDT Han-Chul Kim, Jae-Hong Park, Jung-Jae Lee, Han-Beol Kang, Key-Young Sung, and Kwang-Won Seul(KINS) S PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Preliminary Assessment of Depressurization Performance of Reactor Building Spray Dedicated to Severe Accident Chang-Hwan Park and Jae-Sun Jo(FNC Tech.) Sun-Hong Yoon(KEPCO E&C) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Baseline Confirmation for MELCOR DB Construction Y.M. Song and K.I. Ahn(KAERI) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Steady State Analysis Using the MELCOR1.8.6 Model for the SMART Severe Accident Analysis Jaecheol Kim and Gunhyo Jung(FNC Tech.) Hanchul Kim(KINS) PDF보기 -
2010-Autumn 제5분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Conservative Estimation of In-vessel Retention for High Power Reactors Sang Ho Kim and Soon Heung Chang(KAIST) PDF보기 -
Last Modified : 1998-Autumn