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학술발표회 논문집 (ISSN: 3140-1864)

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:20 Halla Hall B Numerical Assessment of Flooding Safety System Mitigation Performance During an Out-CV LOCA Scenario in a Small Modular Reactor using MELCOR Code Hyo Jun An, Jae Hyung Park, Yujin Kim, Sehee Kwon, Hyunjun Chung, Yuseong Go, JinHo Song, Joon Eon Yang, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:40 Halla Hall B Numerical Investigation of a Dual-Tank Drain System under Marine Environment Hyeon Ji Kim and In Cheol Bang(UNIST) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:00 Samda Hall A Estimated Available Time for SBLOCA with Safety Injection Failure in APR1000 JEE YEA HONG, MIN SEOK LEE, and UNG SOO KIM(KEPCO E&C) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:20 Samda Hall A Analysis of Loss of Ultimate Heat Sink considering Cliff-Edge Effect in APR1000 YouNyeong Seol, DongWi Kim, MinSeok Lee, and SeokJeong Park(KEPCO E&C) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:40 Samda Hall A Assessment of the Boiling Heat Transfer Model for Horizontal Tube Bundles in the Passive Auxiliary Feedwater System of the SPACE Code Mun Ryeol Park, Do Yeon Kim, Myung Jun Kim, Jin Gy Beak, and Dong In Yu(PKNU), Hyeok Jun Son(KOCEN), Hae Min Park and Jong Hyuk Lee(KAERI) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:00 Samda Hall A Validation of MARS-KS Models for the Passive Containment Cooling System of i-SMR and Application to Containment Transient Analysis Changyong Jung, Yeon-Gun Lee, and Hyeonjo Kim(Sejong Univ.) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:20 Samda Hall A Development of a MATLAB-Based Lumped-Parameter Dynamic Analysis Methodology for Hydraulically-Operated PECCS Valves of i-SMR JeongWon Han, YoungSeok Bang, and YoungJae Park(FNC Tech.) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:00 Samda Hall A Preliminary Numerical Analysis of Heat Load Sharing Characteristics between PAFS and PCCS under PECCS Failure Conditions Yujin Kim, Hyo Jun An, JinHo Song, Joon Eon Yang, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5E : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:20 Samda Hall A Numerical Prediction of DNB in a Rolling 2×2 Rod Bundle with Tilted Rotation Axis Namkyu Ryu and Byeongjae Kim(CNU) PDF보기 PPT보기
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:30 302 Modeling and Simulation with AMESIM Code and Comparison with MARS-LMR Code for a PGSFR IHTS Min Gyu Park, Seon Gon Kim, and Jae Ho Jeong(CAU) PDF보기 -
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 13:50 302 Sensitivity Study on the Natural Convection Test in the Molten Salt Reactor Experiment using the GAMMA+ Code Hyun-Sik Park, Nam-il Tak, and Hong-Sik Lim(KAERI) PDF보기 PPT보기
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 14:10 302 Comparative Analysis of Pump Sizing Requirements Molten Salt Systems Sunghyun Yoo, Gihyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 14:50 302 Coolability Evaluation of a Molten Salt Pool in MSR Containment Vessel under Decay Heat Jaemin Han, Ye Hwan Chun, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 15:10 302 Development of the Mechanistic Critical Heat Flux Prediction Methodology for Tube and Annulus Geometries Min Seo Son, Yongsuk Choi, Tae Young Yang, Gi Won Bae, and Hyoung Kyu Cho(SNU) PDF보기 -
2026-Spring 5F : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 15:30 302 Analytic Investigation on Drying Behavior of Water Film Spread on the Heated Metal Plate Soon-Joon HONG and HyeonMin SEO(FNC Tech.) PDF보기 -
Last Modified : 1998-Autumn