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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Enhancement of Heat Transfer in Steam Generator using Turbulentization at Unique Geometry Joonyoung Sung(HGU) and Jaeyoung Lee(HGU) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Analysis of Natural Circulation in a parallel-channel for single phase flow instability with RELAP5/MOD3 Ki Moon Park(KAIST) and Jeong Ik Lee(KAIST) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) The Sensitivity Analysis of Pressure Tube Creep Rates for Dryout Power Euiseung Ryu(KHNP CRI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Application of MATRA for Low Flow Subchannel Analysis - PNL 7x7 Blockage Test Kyong-Won Seo(KAERI), Hyuk Kwon(KAERI), Seong-Jin Kim(KAERI), Juhyung Lee(KAERI), and Dae-Hyun Hwang(KAERI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Numerical Study of Thermal Hydraulic behavior of Moisture Separator of Steam Generator by CUPID Code Jae Ryong Lee(KAERI), Yun Je Cho(KAERI), Yong Shin Lee(KNFC), and Han Young Yoon(KAERI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Code Evaluation on the Conservative Critical Flow Models in SPACE3.0 Suk-Ho Lee(KHNP CRI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Development the DEC PIRT for APR1400 MSGTR_ Bum Soo Youn(KHNP CRI), Dong Hyuk Lee(KHNP CRI), and Jae Hwa Koh(KHNP CRI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Comparing different wall heat transfer packages in the pre-CHF regime of various system analysis codes Sung Gil Shin(KAIST), Min-Gil Kim(KAIST), and Jeong Ik Lee(KAIST) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Applicability of two-fluid model in predicting onset of flow instability in a narrow rectangular cooling channel under low pressure Jong-Pil Park(KAERI), Hyeonil Kim(KAERI), and Suki Park(KAERI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Simple Numerical Study of Molten Metal Fuel Behavior Inside Channel using Explicit Finite Difference Method Sungbo Moon(UNIST), Hyo Heo(UNIST), Dong Wook Jerng(Chung-Ang Univ.), and In Cheol Bang(UNIST) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Study for Thermal Hydraulic and Radiological Effects on Main Steam Line Break in Westinghouse type Nuclear Power Plants Seung-Chan Lee(KHNP CRI) and Duk-Joo Yoon(KHNP CRI) PDF보기 -
2017-Spring 5N : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Swirling Performance of Rotational Mixing Vane in Subchannel using CFD Haneol Park(UNIST), Han Seo(UNIST), and Incheol Bang(UNIST) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Validation test of computational code for corium pool behavior in the lower plenum of the reactor pressure vessel against LIVE experiments Donggun Son(KAERI), Jin-Sung Jang(KAERI), Jun-Ho Bae(KAERI), Rae-Joon Park(KAERI), Dong-Ha Kim(KAERI), and Hwan-Yeol Kim(KAERI) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) A Behavior of Lower Head by Ex-Vessel Steam Explosion in External Reactor Vessel Cooling Jihoon Bae(KMOU), Jongrae Cho(KMOU), Kwanghyun Bang(KMOU), and Hyoungtak Kim(KMOU) PDF보기 -
2017-Spring 5O : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Conversion Ratio of Molten Corium in TROI Steam Explosion Experiment Seong-Wan HONG, Young-Su NA, and Rae-Joon PARK(KAERI) PDF보기 -
Last Modified : 1998-Autumn