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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I The Development of Phenomena Identification and Ranking Table for Innovative Small Modular Reactor Yerim Park, MinJeong Kim and Dong-Hyuk Lee(KHNP) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Study on the Effect of Heat Removal Ratio of PAFS and PCCS on Core Level in i-SMR Using Simplified Model Dong-Hyuk Lee and Yerim Park(KHNP) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Study of the Passive Steam Generator Cooling System Operation in WH 3-Loop NPPs Junkyu Song and Seyun Kim(KHNP) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Calculation of Outside Containment Compartment Temperature using GOTHIC Code KYUNGHO NAM(KHNP) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Analysis on the Inadvertent Opening of Spring-assisted Spool Valve due to Leakage JeongWon Han, YoungSeok Bang, YouCho Choi, and YoungJae Park(FNC Tech.) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Validation of SPACE Code for Flashing-Induced Instability Using CIRCUS Experiments Minyoung Park and Jong-Hyuk Lee(KAERI) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Prediction of Hot Channel Factor in the OPAL Research Reactor as a Reference for Plate Type Fueled Research Reactor JunYoung Lim and JaeHyun Cho(CAU), Kiwon Song(KAERI) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Prediction of DNB in the Tube and Annulus Channel at High Pressure Using Eulerian-Eulerian Two-phase Flow Model in STAR-CCM+ Tae Young Yang, Giwon Bae, and Hyoung Kyu Cho(SNU) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Review of Passive Safety System of ESBWR, VVER and RR-SMR Seongwan Hong, Soon-Joon Hong, Youngjae Park, and Jan Hruskovic(FNC Tech.) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Preliminary Review on the Application of the Single Failure Criterion to Passive Safety Systems Sera Jeon, Seong-Su Jeon, and Youngjae Park(FNC Tech.) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Effect of Hot Channel Factors and Flow Velocity on ONB Temperature Margin Junyoung Seo and Jaehyun Cho(CAU), Kiwon Song(KAERI) PDF보기 -
2025-Autumn 5H : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Assessment of Molten Salt Pool Solidification with Decay Heat Using a 2D CFD-Informed 1D Steady-State Heat-Transfer Model Jaemin Han, Ye Hwan Chun, Juhyeong Lee, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2025-Autumn 5I : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Application of a Mechanistic Liquid Film Model to Advance Condensation Heat Transfer Analysis in Passive Heat Sinks of Containment Jeong Hun Kang and Yeon-Gun Lee(Sejong Univ.) PDF보기 PPT보기
2025-Autumn 5I : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Evaluation of Multiple SGTR at the Innovative SMR using SPACE Code Hyunjoon Jeong(KHNP) PDF보기 -
2025-Autumn 5I : 원자력 열수력 (Nuclear Thermal Hydraulics) 10.30(Thu) 13:00 컨벤션홀 I Validation of the Steam Condensation Region Model (SCRM) for CFD Analysis of Steam Discharge in the IRWST Choengryul Choi, Dae Kyung Choi, and Sung Man Son(Elsoltec), Kwang-Chu Kim(KEPCO E&C) PDF보기 -
Last Modified : 1998-Autumn