학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2020-Spring | 6F : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | CFD Analysis for a Westinghouse Natural Circulation Experiment during Severe Accidents | Hyung Seok Kang, Sung Il Kim, Eun Hyun Ryu, and Kwang Soon Ha(KAERI) | PDF보기 | - |
| 2020-Spring | 6F : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Preliminary Aerosol Concentration Effect Modeling in Pool Scrubbing Code | Yo Han Kim and Yong Hoon Jeong(KAIST) | PDF보기 | - |
| 2020-Spring | 6F : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Monte-Carlo Strategy of Spray Droplet for LOCA Dose Estimation by Decontamination Factor | Seung-Chan LEE(KHNP CRI) | PDF보기 | - |
| 2020-Spring | 6F : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | The Effects of LOCA Dose Estimation by Spray Droplet Surface Area | Seung-Chan LEE(KHNP CRI) | PDF보기 | - |
| 2020-Spring | 6G : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Verification Study on New Safety Goal for Avoiding Long-term Off-site Contamination | Kyuntae KIM, Yongjin LEE, Dongwon LEE, Seoungwoo LEE, and Dohyoung KIM(KINS) | PDF보기 | - |
| 2020-Spring | 6G : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Severe Accident Analysis in Mid Loop Operation at OPR1000 Using MELCOR | Yerim Park, Hoyoung Shin, Youngho Jin, Dong Ha Kim, and Moosung Jae(HYU) | PDF보기 | - |
| 2020-Spring | 6G : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Assessment of Source Term for ISLOCA Using MELCOR | Seungwoo Kim, Youngho Jin, Dong Ha Kim, and Moosung Jae(HYU) | PDF보기 | - |
| 2020-Spring | 6G : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Design of the Experimental Facility for the RVACS Natural Circulation of the PGSFR, SINCRO-3D | Min Ho Lee and In Cheol Bang(UNIST), Dong Wook Jerng(CAU) | PDF보기 | - |
| 2020-Spring | 6G : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | CFD Modeling for Validation of the 1/7th Scale Steam Generator Inlet Plenum Mixing Experiment | Kukhee Lim and Yong Jin Cho(KINS), Cheongryul Choi and Dae Kyung Choi(Elsoltec) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Use of 650℃ Peak Cladding Temperature as a Design Goal for Design Basis Accident 1 | Kyung-min Yoon and Jae-il Lee(KEPCO NF), Do-hwan Lee(KHNP) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Maintenance Planning of Complex Power Grids based on Critical Cascading Failure Scenarios | Eujeong Choi(KAERI), Junho Song(SNU) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | The Study for Dose Effect Analysis of Control Rod Ejection Accident | Seung-Chan LEE, Tae-Woo Kim, Min-Jeong Kim, and Duk-Joo Yoon(KHNP CRI) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Experimental Study to Detect Bubble in Bubbly flow Using Ultrasonic Pulse-echo Method | Geoseong Na, Ji-Hwan Park, Hongrae Jo, and Daeseong Jo(KNU) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Improvements on Fire Human Reliability Analysis Procedure for Korean Nuclear Power Plants Through Case Study | Sun Yeong Choi, Dae Il Kang, and Yong Hun Jung(KAERI) | PDF보기 | - |
| 2020-Spring | 6H : 원자력 안전 (Nuclear Safety) | 7.9(Thu)~7.10(Fri) | On-line | Risk Assessment of Main Control Room Fires for Domestic NPP Based on NUREG-2178 | Dae Il Kang and Yong Hun Jung(KAERI) | PDF보기 | - |
Last Modified : 1998-Autumn
