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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2019-Spring 6D : 원자력 안전 (Nuclear Safety) 5.23(Thu) 12:00 203 (3F) Steam Removal Phenomenon Inside the Containment of Nuclear Power Plants using Silica Gel Considering Initial Steam Partial Pressure Conditions Up to a Design Limit Dong Hoon Kam and Yong Hoon Jeong(KAIST) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 09:00 203 (3F) (초청발표 1) The Fukushima Accident - Past, Present and Future JinHo Song(KAERI) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 09:40 203 (3F) Phenomena Identification and Ranking Tables for Inter-System Loss of Coolant Accident Kwang Soon Ha, Byeonghee Lee, Jin Ho Song, Sung Il Kim, Yong Mann Song, and Youngsu Na(KAERI) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 10:00 203 (3F) Human Reliability Analysis for Level 2 PSA: Qualitative Information Analysis of Severe Accident Management Guidelines under Postulated Accident Scenarios Jaewhan Kim and Jaehyun Cho(KAERI), Keo-hyoung Lee(FNC Tech.) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 10:20 203 (3F) How to Estimate the Effect of Inter-Unit Release of Radioactive Materials in Multi-Unit Site Jae Young Yoon and Dong-San Kim(KAERI) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 11:00 203 (3F) An Assessment of Fission Product Release Mitigation by CFVS at ECF using MELCOR 2.2 Seungwoo Kim, Dohyun Lim, Youngho Jin, Dongha Kim, and Moosung Jae(HYU) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 11:20 203 (3F) An Evaluation of Severe Accident Management Strategy Using PORVs in SGTR Accident Hoyoung Shin, Yerim Park, Youngho Jin, Dong-Ha Kim, and Moosung Jae(HYU) PDF보기 -
2019-Spring 6E : 원자력 안전 (Nuclear Safety) 5.24(Fri) 11:40 203 (3F) Computer Code ROSHNI’s Predictions of CANDU Severe Accident Progression and Its Confirmation of Severity of Reactor Design Omissions, Source Term Vulnerabilities and Avoidable Risks Sunil Nijhawan(Prolet Inc) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 13:30 203 (3F) Evaluation of Improved Fission Product DFs Model in MAAP-ISAAC 4.03 Code during MSGTR Accident Chul-Kyu Lim, Sook-Kwan Kim, and Sang-Koo Han(ACT Co.,), Kwang-Il Ahn(KAERI), Seok-Won Hwang(KHNP CRI), Chan-Young Paik(FAI) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 13:50 203 (3F) Current Status of a Module for Iodine Behavior in Containment Jaehoon Jung, Kwang soon Ha, and Sung Il Kim(KAERI) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 14:10 203 (3F) Decontamination Factor Prediction Using Artificial Neural Networks Method Seongmin Lee and Yong Hoon Jeong(KAIST) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 14:30 203 (3F) Analyses of Fission Product Retention under ISLOCA using MELCOR for APR1400 Keo-hyoung Lee(FNC Tech.), Kwang-il Ahn(KAERI), Seok-won Hwang(KHNP CRI) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 14:50 203 (3F) Computational Study of Lean Limit Flames in Hydrogen Mixtures to Investigate Flame Propagation Characteristics Joongoo Jeon, Yeon Soo Kim, Hoicul Jung, and Sung Joong Kim(HYU) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 15:30 203 (3F) Three-Dimensional Numerical Study on Hydrogen Behavior in CANDU Reactor Building in a Severe Accident Taehyub Hong and Jong Wook Go( KHNP) PDF보기 -
2019-Spring 6F : 원자력 안전 (Nuclear Safety) 5.24(Fri) 15:50 203 (3F) Potential Safety Benefit of Oxidation-Resistant CrAl Coated Zr Cladding Under Severe Accidents such as TMI and SBO Conditions T.H. CHUN, C.H. SHIN, and J.H. YANG(KAERI) PDF보기 -
Last Modified : 1998-Autumn