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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Autumn 6D : 원자력 안전 (Nuclear Safety) 10.31(Fri) 09:40 607 Sensitivity Analysis of Bus Duct Damage Limits Dae Il Kang, Kyungho Jin, and Yong Hun Jung(KAERI), Chi Young Lee(Pukyong National Univ.) PDF보기 -
2025-Autumn 6D : 원자력 안전 (Nuclear Safety) 10.31(Fri) 10:00 607 Proposed Framework for Fire Risk Assessment of Main Control Boards Considering Loss of Control (LOC) Sun Yeong Choi, Dae Il Kang, and Yong Hun Jung(KAERI) PDF보기 -
2025-Autumn 6D : 원자력 안전 (Nuclear Safety) 10.31(Fri) 10:20 607 Wildfire Probabilistic Safety Assessment of Off-site Power System Considering Local Wildfire Duration YeonWoo Choi and Seunghyun Eem(Kyungpook National Univ.), Shinyoung Kwag(Hanbat National Univ.), Daegi Hahm(KAERI) PDF보기 -
2025-Autumn 6D : 원자력 안전 (Nuclear Safety) 10.31(Fri) 11:00 607 A Semi-Detailed Method for Fire Scenario Analysis in Fire PSA Yong Hun Jung, Kyungho Jin, and Dae Il Kang(KAERI) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Qualitative Safety Analysis for a Guaranteed Shutdown Condition of CANDU 6 Reactor Dongwook Kho(KHNP) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Development of Open Prototype PSA Model Using IAEA iPWR Simulator Jeongwoo Jae, Dohun Kwon, and Gyunyoung Heo(KHU) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Sensitivity Analysis of Internal Flooding Probabilistic Risk Assessment Considering Recent Pipe Rupture Frequencies and Aging Factors in the Fire Protection and Service Water Systems of an APR1400 Nuclear Power Plant Jina Jang(KEPCO E&C) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I An Update on the State of Knowledge (SoK) for the Maritime Molten Salt Reactor (MSR) Phenomena Identification and Ranking Table (PIRT) Young Jin Go, Kyung Rae Yook, Moon Hyeok Kang, and Jeong Ik Lee(KAIST) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Applicability of TI-RIPB Methodology to Maritime MSR Seung-Cheol Jang and Sung-Il Kim(KAERI) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Quantitative Assessment Methodology of Safety-Critical Software Reliability in Digital I&C Systems Seung-Cheol Jang, Sung-Min Shin, Jin-Kyun Park, and Jong-Gyun Choi(KAERI) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Accessibility Assessment of Support Personnel to Hanul NPP during a Mw 7.0 Earthquake Gungyu Kim and Seunghyun Eem(Kyungpook National Univ.), Shinyoung Kwag(Hanbat National Univ.), Jeong-Gon Ha and Jinhee Park(KAERI) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I IR Thermography Analysis for the Structural Integrity Assessment of CFRP-Reinforced Concrete in Nuclear Containment Buildings Keun-Chan Cho, Ha-Rin Jeong, Sanjeeb Lama, and Joo-Hyung Kim(Inha Univ.), Ho-Chul Shin(KAERI) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Comparative Analysis of the TI-RIPB and Conventional LWR Safety Analysis Reports Taejoong Kim, Geon Kim, Dayeong Jung, and Gyunyoung Heo(KHU) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Applicability Assessment of the Top-Hat Jet_Plume Model for Hydrogen Explosion Risk in NPPIntegrated Hydrogen Facilities YOUNGHUN SHIN, INCHUL RYU, and KILJUNG KIM(KEPCO E&C) PDF보기 -
2025-Autumn 6E : 원자력 안전 (Nuclear Safety) 10.30(Thu) 13:00 컨벤션홀 I Advanced Prediction of Nuclear Power Plant Transients via Operator Action-Timing Feature Engineering Daehyung Lee, Yongju Cho, Chungwon Seo, and Byung Jo Kim(KEPCO E&C) PDF보기 -
Last Modified : 1998-Autumn