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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of the Passive Condensation Cooling Tank of the PASCAL Test Facility Using the Component Thermal-hydraulic Analysis Code CUPID Hyoung Kyu Cho, Seung-Jun Lee, and Han Young Yoon(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Flow Excursion Analysis in PAFS Soon Joon HONG and Kyung Jin LEE(FNC Tech.) Jong CHEON and Han Gon KIM(KHNP CRI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of Effect of N2Gas on the Cooling Capability of Passive Auxiliary Feedwater System (PAFS) in APR+ Yun-Je Cho, Kyong-Ho Kang, and Byong-Jo Yun(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Thermal-hydraulic Analysis of SGTR for Supporting PSA in APR+ Sang Hee Kang(KHNP CRI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Validation of the Condensation Model in the CAP Code with the BFMC-D1 and D12 Tests Moonhee Choi, Dongin Yu, Sanghun Park, Jinho Park, Hyun Sun Park, and Moo Hwan Kim(POSTECH) Hoon Cho PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Simulation of Cold-leg Small Break LOCA for ATLAS Using SPACE Code Byoung Jae Kim, Hyoung Tae Kim, and Kyung Doo Kim(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Verification of the SPACE Code for Separate Effects Tests Myung Taek Oh, Chan Eok Park, and Jong Joo Sohn(KEPCO E&C) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Effect of Flow Blockage and Fuel Relocation on Core Cooability during Loss of Coolant Accident Seunghoon Ahn(KINS) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Feasibility Study for Applicability of the Wavelet Transform to Code Accuracy Quantification Jongrok Kim and Ki-Yong CHOI(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Accident Analysis for TMI-2 Using MELCOR Moon-Oh Kim and Hee-Do Lee(ACT co., Ltd.) Jeong-Wha Park and Seong-Wan Hong(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Design of Passive Containment Cooling System of PWR Using Multi-pod Heat Pipe Jun-Seok Park and Sang-Nyung Kim(KHU) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Effect of the Geometric Scale on the Critical Heat Flux for The Top of the Reactor Vessel Lower Head Hae Min Park and Yong Hoon Jeong(KAIST) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Overall Consideration to Flood Liquid Gallium in Reactor Cavity for IVR-ERVC Seong Dae Park, Sarah Kang, Seung Won Lee, Seong Man Kim, Han Seo, and In Cheol Bang(UNIST) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) CFD Analysis for a Hydrogen Flame Acceleration in the IRWST Facility Hyung Seok Kang, Kwang-Soon Ha, Sang-Baik Kim, and Seong Wan Hong(KAERI) PDF보기 -
2012-Spring 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Sensitivity Study on Hydrogen Generation in APR1400 RPV by MELCOR Code Vo Thi Huang, Tae-Woon Kim, Jinho Song, and Bo Wook Rhee(KAERI) PDF보기 -
Last Modified : 1998-Autumn