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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Model and Estimation of ATWS Frequency for the APR-1400 Reactor Seung-Cheol Jang(KAERI) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line A Behavioral Scientific Proposal to Revise the Multi-Unit Probabilistic Risk Assessment for Improving Risk Communication and Public Acceptance on Nuclear Yong Hee Lee(KAERI) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Analysis of Success Criteria for POS5 in OPR-1000 using MARS-KS Dohun Kwon, Eojin Jeon, and Gyunyoung Heo(KHU) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Fuzzy Aggregation Approach for Estimating Severe Accident Phenomenon Probability Young A Suh, Kiwon Song, and Jaehyun Cho(KAERI) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Suggestion of a Nuclear Safety Culture Monitoring Process Younggab Kim and Jeongjin Park(KHNP CRI) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Resilience Concept for Evaluating Radiological Emergency Plan Gibeom Kim, Kyusik Oh, and Gyunyoung Heo(KHU) PDF보기 -
2020-Spring 6I : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line PSA Methodology for Classification of Practical Elimination for APR1400 in Terms of Source Term Category of Level 2 PSA Jaegab Kim, Ho Seok, Yangsoo Kim, Sangho Kang, and Inchul Ryu(KEPCO E&C), Horim Moon(KHNP CRI) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Preliminary Sensitivity Analyses on the Criticality of Fuel Assembly during Late Phase of a Severe Accident Yoonhee Lee and Yong Jin Cho(KINS) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Simulation of a Conjugate Heat Transfer Using a preCICE Coupling Library dehee Kim and jongtae Kim(KAERI) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Experimental Study on the Heat Transfer Characteristics of CNF Nanofluids during Quenching Hundong Choi, Hyelyung Lee, Minjung Choi, Yeeun Cho, and Kwon-yeong Lee(HGU) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line CFD-aided Estimation of the Natural Circulation Flow Rate in External Reactor Vessel Cooling via 1-D Simulation Using MARS-KS Min Seop Song and Eung Soo Kim(SNU), Il Woong Park and Yeon-Gun Lee(JNU) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Preliminary CFD Analysis for a Natural Circulation Flow between a Reactor and Steam Generator in an OPR100 Hyung Seok Kang, Sung Il Kim, Eun Hyun Ryu, and Kwang Soon Ha(KAERI) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line MELCOR Simulation of in-vessel Mitigation Strategies by Multiple Actions Using Mnte Carlo Method Wonjun Choi and Sung Joong Kim(HYU) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Simulation of Jet Breakup in Lower Plenum with Internal Structure Using Smoothed Particle Hydrodynamics Hoon Chae, So-Hyun Park, and Eung Soo Kim(SNU) PDF보기 -
2020-Spring 6J : 원자력 안전 (Nuclear Safety) 7.9(Thu)~7.10(Fri) On-line Procedure Development of IVR-ERVC Analysis and Its Results in SMART100 Rae-Joon Park, Donggun Son, Hyung Seok Kang, and Sang Mo An(KAERI) PDF보기 -
Last Modified : 1998-Autumn