학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | An Evaluation of the Steam Explosion Model of MC3D Code | Ik Kyu Park, Jong Hwan Kim, and Seong Wan Hong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Validation of Numerical Schemes in a Thermal-Hydraulic Analysis Code for a Natural Convection Heat Transfer of a Molten Pool | Jongtae Kim, Kwang Soon Ha, Hwan Yeol Kim, Rae-Joon Park, and Jin Ho Song(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Development of the Preliminary MELCOR1.8.6 Model for the SMART Severe Accident Analysis | Jaecheol Kim and Gunhyo Jung(FNC Tech.) Hanchul Kim(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Uncertainty Analysis of the Molten Corium-Concrete Interaction during Severe Accidents in Typical PWR | Soo Yong Park and Kwang Il Ahn(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Computational Aid of CANDU Reactor Severe Accident Management Strategies for Containment Integrity | Young Choi, D. H. Kim, S. D. Kim, S. Y. Park, and Y. H. Jin(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Results of OECD-NEA THAI Test HM-2 Benchmark Study with MELCOR Code | Jung-Jae Lee, Han-Chul Kim, and Key-Yong Sung(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | APR1400 Containment Simulation with CONTAIN Code | Moonkyu Hwang and Bub Dong Chung(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Estimation of Common Cause Failure Parameters for Emergency Service Water System Pump of Kori Unit 2 | Dae Il Kang, Mee Jung Hwang, Sang Hoon Han, and Jin Hee Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Sensitivity Analyses of Core Damage Frequency on the Design Alternatives for SFR-600 Conceptual Design | Tae Woon Kim, Sang Hoon Han, and Hae-Yong Jeong(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Technical Considerations for the Systems Analysis in SMART PSA | NamChul Cho and Chang-Ju Lee(KINS) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Proposed Approach for Enhancing Design Safety Assurance of Future Plants | Kju-Myeong Oh, Sang-Kyu Ahn, and Chang-Ju Lee(KINS) Inn Seock Kim(ISSA Tech.) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Study on LOCA Frequency and Contribution to Risk of Nuclear Power Plant | Seong Soo Choi, Dong Sik Jin, and Poong Oh Kim(ACT Co.,Ltd.) Inn Seock Kim(ISSA Tech.) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | A Study on the Regulatory Requirement of Event Frequency Change by Facility Improvement and Modification in Wolsong Unit 1 | Kilyoo Kim and Jinhee Park(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Comparison between Heinrich's Law and the Number of Events in Domestic Nuclear Power Plants | Sun Yeong Choi and Joon-Eon Yang(KAERI) | PDF보기 | - | ||
| 2010-Spring | 제 5 분과 : 원자력열수력 및 안전(Thermal Hydraulics and Safety) | Assessment of In-Core Damage for Feeder Stagnation Break in CANDU | Jong Yeob Jung and Joo Hwan Park(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
