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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 09:00 201호 (2F) Accident Analysis of Micro-Nuclear Reactor by Non-Injection Systems as Portable Submergence Reactor (PSR): Approaching to Concept of Perfect Safety Tae Ho Woo and Chan Young Cho (CUK) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 09:20 201호 (2F) Procedure Development of Drone Risk Analysis YongTae Kim, YunSeon Chung, GeumYong Lee, and WooSik Jung(Sejong Univ.) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 09:40 201호 (2F) Numerical Investigation of Nonlinear Concrete Fracture Behavior using Cohesive Zone Modeling Habeun Choi(KAERI), Kyoungsoo Park(Yonsei Univ.) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 10:00 201호 (2F) The Hydrogen Recombination Characteristics of a Grid-Type PAR during a Spray Operation Jongtae Kim, Seongho Hong, Ki-Han Park, Jin-Hyuk Kim, and Jeong-Yoon Oh(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 10:20 201호 (2F) CFD Simulation of Boiling Two-Phase Flows with Different Thermophysical Properties for Core-Catcher Cooling System Sangmin Kim, Keunsang Choi, and Jeahoon Jung(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 11:00 201호 (2F) Integral Test of Ex-vessel Debris Bed Formation in a Pre-flooded Reactor Cavity Sang Mo An, Seokgyu Jeong, Ki Han Park, Keun Sang Choi, and Chang Wan Kang(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 11:20 201호 (2F) Preliminary Modelling of Ex-vessel Debris Bed Formation in a Pre-flooded Reactor Cavity Seokgyu Jeong, Sang Mo An, Ki Han Park, Chang Wan Kang, and Keun Sang Choi(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 11:40 201호 (2F) Characteristics of Single and Two-phase Flows through Porous Particle Beds Jong Seok Oh, Min Gu Kang, and Dong Eok Kim(CAU), Sang Mo An and Hwan Yeol Kim(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 12:00 201호 (2F) Coolability Analysis of Ex-vessel Corium in OPR1000 Pre-flooded Reactor Cavity Jaehoon Jung, Donggun Son, and Sang Ho Kim(KAERI) PDF보기 -
2022-Spring 6C : 원자력 안전 (Nuclear Safety) 5.19(Thu) 12:20 201호 (2F) COCCI for a Simulation of Molten Core and Concrete Interaction During a Severe Accident Sang Ho Kim, Jaehyun Ham, Hwan-Yeol Kim, Rae-Joon Park, and Jaehoon Jung(KAERI) PDF보기 -
2022-Spring 6D : 원자력 안전 (Nuclear Safety) 5.20(Fri) 09:00 201호 (2F) Study on Degradation of NBR under Simulated Post-Accident Environment of Severe Accident Inyoung Song and Ji Hyun Kim(UNIST), Deahwan Kim, Daewon Cho, Taehyun Lee, and Kyungha Ryu(KIMM) PDF보기 -
2022-Spring 6D : 원자력 안전 (Nuclear Safety) 5.20(Fri) 09:20 201호 (2F) Measurement of the Heat Load Imposed on the Reactor Vessel Depending on the Debris Bed Under an IVR Condition Joonsoo Park, Haekyun Park, Seong-Il Baek, and Bumjin Chung(KHU) PDF보기 -
2022-Spring 6D : 원자력 안전 (Nuclear Safety) 5.20(Fri) 09:40 201호 (2F) Numerical Analysis on IVR-ERVC using Lagrangian CFD – Modeling & Preliminary Results Tae Hoon Lee, So Hyun Park, Hoon Chae, and Eung Soo Kim(SNU), Yeon-Gun Lee(JNU) PDF보기 -
2022-Spring 6D : 원자력 안전 (Nuclear Safety) 5.20(Fri) 10:00 201호 (2F) Elemental Analysis of Metallic and Non-metallic Aerosols Formed by Reaction of Molten Iron with Concrete Jei-Won Yeon, Minsik Kim, and Jae Hoon Kim(KAERI) PDF보기 -
2022-Spring 6D : 원자력 안전 (Nuclear Safety) 5.20(Fri) 10:20 201호 (2F) Aerosol Deposition Characteristics inside Horizontal Piping Woo Young Jung, Ji Hun Kang, Dong Young Lee, Min Beom Hur, Jong Chan Lee, Hyun Chul Lee, Dong Hyun Lee, and Doo Yong Lee(FNC Tech.), Byonghee Lee and Kwang Soon Ha(KAERI) PDF보기 -
Last Modified : 1998-Autumn