학술발표회 논문집 (ISSN: 3140-1864)
| Year | Div | Date/Time | ROOM | Title | Author | Abstract File | Presentation File |
|---|---|---|---|---|---|---|---|
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Evaluation of CHF Correlation Model Performance in MATRA for Various Rod Bundle Geometries | Seojun Park and Kyung Mo Kim(KENTECH) | PDF보기 | PPT보기 |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Hydrodynamic Feasibility Test of Gravity-Driven Drainage in Cartridge-Type Molten Salt Reactor | Seolhui Kim, Ik Jae Jin, Doyeong Lim, and In Cheol Bang(UNIST) | PDF보기 | - |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | sCO2 Brayton Cycle Layout Study on Gas-cooled Reactor for Maritime Propulsion | Chanyong Park and Jeong Ik Lee(KAIST) | PDF보기 | - |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Preliminary Analysis of SBLOCA Test for SMART-ITL using the SPACE Code | Yongjae Lee, Hwang Bae, and Jong-Hyuk Lee(KAERI) | PDF보기 | - |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Comparative Assessment of Boiling Heat Transfer Predictability of System Codes MARS-KS and TRACE in Helically Coiled Tubes | Seongman Jeong, Yunseok Lee, and Taewan Kim(INU) | PDF보기 | - |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Numerical Validation of Molten Salt Spill and Solidification Behaviors using ANSYS Fluent and OpenFOAM | Ye Hwan Chun, Juhyeong Lee, JinHo Song, and Sung Joong Kim(HYU) | PDF보기 | - |
| 2026-Spring | 5L : 원자력 열수력 (Nuclear Thermal Hydraulics) | 5.7(Thu) 13:00 | Lobby | Assessment of the Heat Transfer Model of a Helically Coiled Tube in MARS-KS and SPACE Codes | Tae Wook Ha and Jong-Hyuk Lee(KAERI) | PDF보기 | - |
| 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 | PPT보기 |
| 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 | PPT보기 |
| 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 | - |
Last Modified : 1998-Autumn
