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) | 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 | - | ||
| 2008-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | CANDU Reactor Severe Accident Management Strategies for Plant Specific Features | Young Choi, D. H. Kim, J. H. Jin, and J. H. Park (KAERI) | PDF보기 | - | ||
| 2008-Autumn | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Validation of MELCOR 1.8.5 Pool Chemistry Model with RTF Experiments | Dong Ju Jang, Chang Wook Huh, and Namduk Suh (KINS) | PDF보기 | - |
Last Modified : 1998-Autumn
