학술발표회 논문집
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:00 | 201A | MODELICA Simulation-Based Probabilistic Assessment of i-SMR Containment Integrity under PCCS Performance Degradation | Seongjun Hong(RPI|HYU), Riyad Hasan and Hyun Gook Kang(RPI), Yeon Ki Chung(RPI|KINS) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:20 | 201A | Human Performance Data Acquisition and Analysis for Multi-Module SMR HRA | Jaeeun Kim, Seong Kyu Park, Dohyeon Kim, and Hongseok Kim(NESS) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:40 | 201A | Development and Demonstration of a Local RAG-Based QA System Using an Open-Source LLM for the SMR Level 1 PSA Report | Hyeonho Byun and Hyeonmin Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 10:00 | 201A | Considerations for Safety Classification of Structures, Systems and Components of Non-LWRs | Gyunyoung Heo, Geon Kim, Taejoong Kim, Dayoung Jung, Minseok Kim, and Jeongwoo Jae(KHU) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 10:20 | 201A | Assessment of Inherent Safety Features and Pressure Integrity of i-SMR during Anticipated Transient Without SCRAM | Gangmin Kim and Jaehyun Cho(CAU), Jin Hee Park(KAERI) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 11:00 | 201A | Determination of Feasible Design Ranges for the Passive Emergency Core Cooling System under LOCA Conditions in a Small Modular Reactor | Juhyeob An and Jaehyun Cho(CAU), Jin Hee Park(KAERI) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 11:20 | 201A | Analysis of Performance Shaping Factors in Multi-Module Operating Environments | Dohun Kwon and Gyunyoung Heo(KHU) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 11:40 | 201A | Quantification of Failure Probabilities for the i-SMR Reactor Vessel Using MELCOR-Based Uncertainty Analysis | Sein Hong and Jaehyun Cho(CAU), Jin Hee Park(KAERI) | PDF보기 | - |
| 2026-Spring | 6A : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 12:00 | 201A | Comparative Analysis of Near-Field Atmospheric Dispersion Models for Nuclear Emergency Planning Zone Sizing | Gibeom Kim and Sung-yeop Kim(KAERI) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:00 | 201B | Comparative Validation of Severe Accident System Codes Through TMI-2 Accident Modeling: Focus on Reflooding Phenomena | Kukhee Lim, Yong Jin Cho, Jeonghyeon Eom, Jun-Soo Lee, Eunho Kim, and Dongju Jang(KINS), Hoon-Goo Oh, Sang-Jin Son, Kyung-Ki Kim, and In-Chul Ryu(KEPCO E&C) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:20 | 201B | Comparative Analysis of Mitigation Effects of Improved DPG SAMG SACRG-01 | JiEun Oh, MiRo Seo, and JeongMin Shin(KHNP), Su Won Lee and Myeong Kwan Seo(FNC Tech.) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 09:40 | 201B | Scenario-Specific Sensitivity of Uncertain Parameters in OPR1000 LOCA: A Comparative Study Using CINEMA | Ok Hyeon Lee, Cheolwoong Kim, JinHo Song, Joon-Eon Yang, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 10:00 | 201B | Effect of Cavity Flooding Level on the Integrity of APR1400 RPV Using MAAP5 | Sangwoo Shin, Miro Seo, Taewoo Kim, and Sun Heo(KHNP) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 10:20 | 201B | Analysis of Uncertainty Parameter Effects on RPV Failure in an MBLOCA Scenario | Tae-woo KIM, Ji-Eun Oh, and Sangwoo Shin(KHNP) | PDF보기 | - |
| 2026-Spring | 6B : 원자력 안전 (Nuclear Safety) | 5.7(Thu) 11:00 | 201B | MCCI Analysis under Pre-flooded Cavity Conditions during Severe Accidents | JunSung Choi, MinChan Kwon, EungSoo Kim, and HyunSun Park(SNU) | PDF보기 | - |
Last Modified : 1998-Autumn
