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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 6F : 원자력 안전 (Nuclear Safety) 5.19(Fri) 10:40 Samda Hall B (3F) Model Sensitivity Analysis for the Effect of State-of-Knowledge Correlation Gyun Seob Song and Man Cheol Kim(CAU) PDF보기 -
2023-Spring 6F : 원자력 안전 (Nuclear Safety) 5.19(Fri) 11:00 Samda Hall B (3F) Strategy Development for Emergency Call Estimation using Agent-Based Platform : PRISM Geon Kim and Gyunyoung Heo(KHU), Jinkyun Park(KAERI) PDF보기 PPT보기
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Preliminary Analysis of LOCA without Safety Injection for APR1400 using CSPACE Computer Code Rae-Joon Park, Dong Gun Son, Jun Ho Bae, and Jaehoon Jung(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) CFD Simulation for Prediction of Flow Characteristics in the Core Catcher by Upward Heat Transfer of Corium Sangmin Kim, Keun Sang Choi, and Jaehoon Jung(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Preliminary Evaluation on Radioactive Material Filtration System Effectiveness under Development Jaehoon Jung, Donggun Son, and SangHo Kim(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Preliminary Results of Multidimensional Modeling of Fuel-Coolant Interactions with Lagrangian-Eulerian Coupling of Melt and Coolant Min-Soo Kim, Dong-Jin Shin, Dong-Ha Kim, and Kwang-Hyun Bang(KMOU) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Effects of Kelvin-Helmholtz Instability on the Triggered Steam Explosion under High Water Level Condition in Reactor Cavity Sang Ho Kim and Seong-Wan Hong(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Preliminary Validation of MCCI Module for Coolability Assessment of Ex-Vessel Corium Jun Sung Choi, Tae Hwan Kim, Jin-Woo Kim, Hyun Sun Park, and Eung Soo Kim(SNU) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Preliminary 1-D Analysis Model on Ex-vessel Corium Coolability in Pre-flooded Reactor Cavity Seokgyu Jeong, Jaehoon Jung, Sang Ho Kim, and Jaehyun Ham(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Comparative Analysis of CCI-3 Test Simulation using COCCI and CORQUENCH Jaehyun Ham, Sang Ho Kim, and Jaehoon Jung(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Benchmark Calculation of OECD/MCCI Experiments using MELCOR and ASTEC Code Hyunha Ahn, Seongnyeon Lee, and Kyubyung Lee(KINS) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Review of Radiological Source Term Evaluation Methodologies to Improve SIRIUS Code in CINEMA Donggun Son, Jun-Young Kang, Sung-Il Kim, Jaehyun Ham, Jun-Ho Bae, and Kwang-Soon Ha(KAERI) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Validation of pH Calculation Model of AnCheBi in the Presence of Organic Impurities Yoonhee Lee and Yong Jin Cho(KINS) PDF보기 -
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) Investigation of Spray Characteristics in TOSQAN-101 Experiment Using OpenFOAM CFD Simulation Keun Sang Choi, Sangmin Kim, Jongtae Kim, and Jaehoon Jung(KAERI) PDF보기 PPT보기
2023-Spring 6G : 원자력 안전 (Nuclear Safety) 5.18(Thu) 13:00 Lobby (3F) An Analytical Study of Hydrogen Combustion and Natural Convection Inside Vertical Plate-type Catalyst Dae-Hyun Kim and Dong-Wook Oh(CSU), Young-Su Na(KAERI) PDF보기 PPT보기
Last Modified : 1998-Autumn