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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 09:40 302 (3F) Validation of RANS based CFD Methodology with STAR-CCM+ Code Using Existing Sodium-Cooled Experimental Data Hanseop Song and Jae-ho Jeong(Gachon Univ.), Junkyu Han(KAERI) PDF보기 -
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:00 302 (3F) Development of Simulation Technique for Crust Formation Calculation using Rigid Body Dynamics Model in Moving Particle Semi-implicit Yun Sik Cho and Sung Joong Kim(HYU) PDF보기 PPT보기
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 10:40 302 (3F) Investigation for Effective Flow Path Designed for Flooding Safety System by Using MELCOR Code Hyo Jun An, Jae Hyung Park, Chang Hyun Song, and Sung Joong Kim(HYU), Jeong Ik Lee and Yonghee Kim(KAIST), PDF보기 -
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:00 302 (3F) Reduced Order Surrogate Modeling for Fast Accident Prediction Jaeseok Heo and Seung-Wook Lee(KAERI), Ha Neul Na and Youngsuk Bang(FNC Tech.), PDF보기 -
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:20 302 (3F) Study of Geometric Parameters for i-SMR Reactor Vessel Auxiliary Cooling System Dong Ho Nguyen, Koung Moon Kim, and Ho Seon Ahn(INU) PDF보기 -
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 11:40 302 (3F) Preliminary Analysis of Two-Phase Instability in Helical Coiled Tube for Helical Steam Generator Seunghwan Oh, Doh Hyeon Kim, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 12:00 302 (3F) Integrate Modeling Analysis of Secondary and Primary System for Small Modular Reactors Jungjin Bang, Seong-Su Jeon, Young Suk Bang, Bub Dong Chung, and Young Seok Bang(FNC Tech.) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:00 302 (3F) A Model of the Bubble Waiting Time in Forced Subcooled Boiling ManhLong Doan, Jeongmin Moon, Jinyeong Bak, Jae Jun Jeong, and Byongjo Yun(PNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:20 302 (3F) Experimental Investigation of the Bubble Behavior Under Rolling Oscillations Myungho Kim and Byoungjae Kim(CNU) PDF보기 PPT보기
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:40 302 (3F) Influence of Inlet Turbulent Boundary Conditions on Bubble Diameter Calculation Erol Bicer, Seong-Su Jeon, Yeon-Jun Choo, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 10:00 302 (3F) Heat Partitioning Model with Bubble Tracking Method Considering Conjugate Heat Transfer Ja Hyun Ku, Heepyo Hong, and Hyoung Kyu Cho(SNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 10:40 302 (3F) Experimental Study for Evaluation of Re-wetting Velocity on Micropillar Structures Using Particle Image Velocimetry (PIV) Technique Hyeon Taek Nam, Hyunmuk Park, Yoomyeong Lee, Seungro Lee, and Donghwi Lee(JBNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:00 302 (3F) Numerical Investigation of DNB for a Subcooled Flow Boiling in an Oscillating Pipe Namkyu Ryu and Byoungjae Kim(CNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:20 302 (3F) A Parametric Study on Pool Boiling CHF Phenomenon in Heaving Conditions: The Effects of Heaving Periods Do Yeon Kim, Su Cheong Park, Seonho Choi, and Dong In Yu(PKNU) PDF보기 -
2023-Spring 5D : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 11:40 302 (3F) Flow Boiling CHF Behavior according to Liquid Subcooling on the ATF-coated Tube Namgook Kim and Sung Joong Kim(HYU) PDF보기 -
Last Modified : 1998-Autumn