학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2024-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.10(Fri) 12:00 | 201A (2F) | Study of LOCA Shine Dose Evaluation Methodology by NAME_LSC Code | Seung-Chan LEE(KHNP) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Preliminary Validation Analysis of Severe Accident Progression on LOCA without Safety Injection of Real Power Plant for CINEMA Computer Code | Rae-Joon Park, Jaehyun Ham, Dong Gun Son, Sangho Kim, and Jaehoon Jung(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Preliminary Analysis on Spreading Distance and Time of Spill Molten Salt using Simple Analytical Model | Rae-Joon Park, Eun Hyun Ryu, Hyoung Tae Kim, and Sung Il Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Estimation of In-Containment Source Terms under Severe Accident for OPR1000 Plant with MAAP5 Code | Byung Jo Kim and Sun Hong Yoon(KEPCO E&C) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Analysis of the Dispersion Distance of Molten Salt in Accident Condition | Sung Il Kim, Hyoung Tae Kim, Hwan Yeol Kim, Rae Joon Park, and Eun Hyun Ryu(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | MELCOR Analysis of TOSQAN ISP-47 Experiment | Hyoung Tae Kim and Jongtae Kim(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Experimental Study on Heat Transfer Characteristics of Downward Facing Inclined Heating Channel | Seokgyu Jeong, Jun-young Kang, Byeonghee Lee, Ki Han Park, Chang Wan Kang, and Seong Ho Hong(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Analysis on the Effect of the In-Vessel Coolant Injection in a Severe Accident of a Small Modular Reactor with a Metal Containment Vessel | Sang Ho Kim, Jaehyun Ham, and Donggun Son(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | A Parametric Concept Model of Ex-Vessel Steam Explosion in the SAFARI Project | Jubin Kim, Eungsoo Kim, and Hyunsun Park(SNU), Sai Raja Gopal Vadlamudi(Helmholtz-Zentrum Dresden-Rossendorf) | PDF보기 | PPT보기 |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Preliminary Severe Accident Analysis of INCV-LOCA in I-SMR Using CINEMA Code | Jaehyun Ham, Sang Ho Kim, and Seokgyu Jeong(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Concept of Corium Coolability Module for Debris Bed Formation during Severe Accidents | Minchan Kwon, Seokwon Whang, Eung Soo Kim, and Hyun Sun Park(SNU) | PDF보기 | PPT보기 |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Calculation of Natural Convection Phenomena in Core Catcher System | Byeonghee Lee and Seokgyu Jeong(KAERI) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Effect of Thermal-hydraulic Coupling on the Fission Products Behavior by Using SIRIUS Modules in CINEMA Code | Yongjun Lee, Chang Hyun Song, Jinho Song, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Performance Evaluation of Conceptual Hybrid Safety Injection Tank under SBO Accident by Using MELCOR Code | Se Hee Kwon, Won Jun Choi, Chang Hyun Song, Jin Ho Song, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2024-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.9(Thu) 13:00 | Lobby (3F) | Current Status of Fission Products Behavior Analysis Code Development in Salt Spill Accident Condition | Sung Il Kim, Hyung Seok Kang, Jae Hyun Ham, Donggun Son, and Kwang Soon Ha(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
