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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 11:40 303B Numerical Prediction of Radial Temperature Distribution in Volumetrically Heated Turbulent Flow for MSR Flow Analysis Moon Hyeok Kang and Jeong Ik Lee(KAIST) PDF보기 -
2026-Spring 5C : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.7(Thu) 12:00 303B In-depth Elucidation of the Relationship between Heat Removal Performance and Operating Parameters using CFD ByungHyun Bae, Je-Hyeong Park, and Jae-Ho Jeong(CAU), Sin-Yeob Kim(KAERI) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:00 Halla Hall B Analyses of Postulated ATWS Events in the Innovative Small Modular Reactor Min Seok Lee, Seok Jeong Park, and Ung Soo Kim(KEPCO E&C) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:20 Halla Hall B A Sensitivity Study of Multiple SGTR at the i-SMR using SPACE Code Hyunjoon Jeong(KHNP) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 09:40 Halla Hall B Orientation Effects on Natural Convection and Temperature Field in Heat Pipe-Cooled Micro-MSR Comparing Triangular and Circular Configurations Seungyoon Lee, Doyeong Lim, and Incheol Bang(UNIST) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:00 Halla Hall B Benchmarking Thermochemistry-Coupled Radionuclide Release in Molten Salt Reactors: cGEMS vs OpenFOAM-GEMS Dowon Lee, Juhyeong Lee, JinHo Song, and Sung Joong Kim(HYU) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 10:20 Halla Hall B Effect of Intra-particle Conduction and Surface Subdivision on High-Temperature Thermal Analysis Sohyeon Ahn and Eung Soo Kim(SNU) PDF보기 -
2026-Spring 5D : 원자력 열수력 (Nuclear Thermal Hydraulics) 5.8(Fri) 11:00 Halla Hall B Assessment of Practical Performance Gains in AI-based CHF Prediction Mooneon Lee, Juhyung Lee, Dae-Hyun Hwang, and Hyouk Kwon(KAERI) PDF보기 -
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 -
Last Modified : 1998-Autumn