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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2024-Spring 6E : 원자력 안전 (Nuclear Safety) 5.10(Fri) 11:00 201A (2F) Application of Emergency Boration System for ATWS Mitigation of Innovative Small Modular Reactor Min Seok Lee, Seong Min Hong, and Hyoung Kyoun Ahn(KEPCO E&C) PDF보기 -
2024-Spring 6E : 원자력 안전 (Nuclear Safety) 5.10(Fri) 11:20 201A (2F) Study on Single CEA Withdralwal Event in a Typical SMR using 3-Dimensional Core Simulation Methodology Yeonguk Jo, Jinwoo Park, and Sungju Cho(KEPCO NF) PDF보기 -
2024-Spring 6E : 원자력 안전 (Nuclear Safety) 5.10(Fri) 11:40 201A (2F) Development of GOD MASTER Program for Accident Dose Effect in DBA/BDBA Seung-Chan LEE(KHNP) PDF보기 -
2024-Spring 6E : 원자력 안전 (Nuclear Safety) 5.10(Fri) 12:00 201A (2F) Study of LOCA Shine Dose Evaluation Methodology by NAME_LSC Code Seung-Chan LEE(KHNP) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Preliminary Validation Analysis of Severe Accident Progression on LOCA without Safety Injection of Real Power Plant for CINEMA Computer Code Rae-Joon Park, Jaehyun Ham, Dong Gun Son, Sangho Kim, and Jaehoon Jung(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Preliminary Analysis on Spreading Distance and Time of Spill Molten Salt using Simple Analytical Model Rae-Joon Park, Eun Hyun Ryu, Hyoung Tae Kim, and Sung Il Kim(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Estimation of In-Containment Source Terms under Severe Accident for OPR1000 Plant with MAAP5 Code Byung Jo Kim and Sun Hong Yoon(KEPCO E&C) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Analysis of the Dispersion Distance of Molten Salt in Accident Condition Sung Il Kim, Hyoung Tae Kim, Hwan Yeol Kim, Rae Joon Park, and Eun Hyun Ryu(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) MELCOR Analysis of TOSQAN ISP-47 Experiment Hyoung Tae Kim and Jongtae Kim(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Experimental Study on Heat Transfer Characteristics of Downward Facing Inclined Heating Channel Seokgyu Jeong, Jun-young Kang, Byeonghee Lee, Ki Han Park, Chang Wan Kang, and Seong Ho Hong(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Analysis on the Effect of the In-Vessel Coolant Injection in a Severe Accident of a Small Modular Reactor with a Metal Containment Vessel Sang Ho Kim, Jaehyun Ham, and Donggun Son(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) A Parametric Concept Model of Ex-Vessel Steam Explosion in the SAFARI Project Jubin Kim, Eungsoo Kim, and Hyunsun Park(SNU), Sai Raja Gopal Vadlamudi(Helmholtz-Zentrum Dresden-Rossendorf) PDF보기 PPT보기
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Preliminary Severe Accident Analysis of INCV-LOCA in I-SMR Using CINEMA Code Jaehyun Ham, Sang Ho Kim, and Seokgyu Jeong(KAERI) PDF보기 -
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Concept of Corium Coolability Module for Debris Bed Formation during Severe Accidents Minchan Kwon, Seokwon Whang, Eung Soo Kim, and Hyun Sun Park(SNU) PDF보기 PPT보기
2024-Spring 6F : 원자력 안전 (Nuclear Safety) 5.9(Thu) 13:00 Lobby (3F) Calculation of Natural Convection Phenomena in Core Catcher System Byeonghee Lee and Seokgyu Jeong(KAERI) PDF보기 -
Last Modified : 1998-Autumn