학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Analysis of Heat Removal Strategy during Reactor Cooling Pump Seal Failure | Ji-Hwan Cha(KINAC) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | The Design Effectiveness of Safety Features of PAFS in APR1000 Level 1 PSA | Jae Gab Kim, Kyung Soo Lee, Jin Kyoo Yoon, and Ho Seok(KEPCO E&C), Ho Rim Moon and Ji Yong Oh(KHNP) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | A Review on the Scope of Accident Management in the Accident Management Plan of Nuclear Power Plant | Min Shin Jung, Dong Hwan Jung, and Hak Kyu Lim(KINGS) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Applying Mobile Equipments Usage to PRA Models | Jung Min Kim, Dong Hwan Jung, and Hak Kyu Lim(KINGS) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Investigation of Existing Studies for Fuel Assemblies to Develop the Methodology for Fragility Analysis | Nahyun Kim and Minkyu Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Floor Response Spectrum Analysis at Different Location of the Same Equipment in the Auxiliary Building of NPP Using 3D FEM | Hyung-Kui Park, Junhee Park, and In-Kil Choi(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Application of Probabilistic Safety Assessment to Korea Research Reactor | Yoon-Hwan Lee and Seung-Cheol Jang(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Development of the Preliminary Risk Profile for Hanaro Research Reactor | Seung-Cheol Jang, Yoon-Hwan Lee, Jeong-Gon Ha, SangBaik Kim, Sora Kim, and Goanyup Lee(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Development of Preliminary MACCS2 Input Model for the Level 3 PSA on the KAERI Site | Sora Kim, Byung-Il Min, Kihyun Park, Kyung-suk Suh, and Seung-Cheol Jang(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Development of the GIS-Based Population Data Conversion Program, POPCON | Seung-Cheol Jang, Sung-yeop Kim, and Sang-Hun Lee(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6E : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Validation & Verification of GIS-Based Population Data Conversion Program (POPCON) | Hyunae Park, Sung-yeop Kim, and Seung-Cheol Jang(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Consideration for Applying Machine Learning in Uncertainty Analysis Method of Severe Accident | Jaehyun Ham, Sang Ho Kim, and Rae-Joon Park(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Preliminary Prediction of Core Exit Temperature for Severe Accident using Machine Learning | Suwon Lee and Youngsuk Bang(FNC Tech.), Jaehyun Cho(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | A CINEMA Code Analysis of the Simplified ERVC Loop in the SMART | Hyoung Tae Kim(KAERI) | PDF보기 | PPT보기 |
| 2021-Spring | 6F : 원자력 안전 (Nuclear Safety) | 5.13(Thu)~5.14(Fri) | On-line | Analysis of IVR-ERVC Evaluation Characteristics for Small Reactor | Rae-Joon Park, Donggun Son, and Sang Ho Kim(KAERI) | PDF보기 | PPT보기 |
Last Modified : 1998-Autumn
