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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Implementation of Turbulence Models into the CUPID Code I. K. Park, J. Kim, H. Y. Yoon, H. K. Cho, and J. J. Jeong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Staggered Semi-implicit Finite Volume Method to Solve 3-dimensional Containment Phenomena Based on Cell and Face Porosity Soon Joon Hong, Su Hyun Hwang, Tae Young Han and Byung Chul Lee (FNC), Choong Sup Byun (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) A Study on MSPI Performance Criteria for CCWS at UCN 3 Using a Generation Risk Assessment Kilyoo Kim, Dae-Il Kang, and Sanghoon Hahn (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of Regulatory PSA Model of Kori Units 3,4 for a Risk Informed Regulation Jin Hee Park, Ho-Gon Lim, Sang Hoon Han, and Dae Il Kang (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Developing a Methodology for Identifying Correlations Between LERF and Early Fatality Kyungmin Kang and Moosung Jae(HYU) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Framework for Quantification of Human Errors in Testing and Maintenance Gyunyoung Heo (KHU), Jin Kyun Park (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Development of a Computational Program for Uncertainty Evaluation of Event Scenario in a PSA Model -MOSAIQUE H. G. Lim and S. H. Han (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) The Use of a Frequency-Consequence Curve for the Licensing of Future NPPs Jongtae Jeong and Meejeong Hwang (KAERI), Kyu-Myeng Oh, Sang-Kyu Ahn, and Chang-Ju Lee (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Estimation of the Risks of Early Fatality for Internal Events in Korean NPPs Do Sam Kim, Jong Soo Choi, and Key Yong Sung (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) HRR Influence Analysis of FDS 5 Using PRISME DOOR Test Data Jongseuk PARK and Chang-ju Lee (KINS), Moonhak, JEE (KEPRI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Investigation of Thermal-hydraulic Variables Affected by the Downstream Effect in the Safety Analysis J. Y. Park and M. W. Kim (KINS) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) An Evaluation of a Film Boiling Heat Transfer Correlation for Fuel Coolant Interactions I. K. Park and S. W. Hong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Evaluation of the Layer Inversion of Melt Pool During the Severe Accident in the APR1400 Kyoung-Ho Kang, Rae-Joon Park, and Seong-Wan Hong (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Expert System Interfaced ASSA Module for Fault Diagnosis for Instrumentation of Accident Conditions Kil-Mo Koo, Yeon-Sik Kim, Won-Pil Beak, and Hee-Yong Kang (KAERI) PDF보기 -
2008-Autumn 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) Offsite Consequence Analysis of the Hypothetical Severe Accident of Ulchin Unit 3, 4 Gunhyo Jung and Juyoul Kim (FNC), Changwook Huh and Namduk Suh (KINS) PDF보기 -
Last Modified : 1998-Autumn