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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Effects of Overlap Length on Pool Boiling from Two Horizontal Tubes in Vertical Alignment Myeong-Gie Kang(ANU) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Suggestion of Empirical Correlation to Evaluate Effects of Tube Inclination on Pool Boiling Heat Transfer of Various Saturated Liquids Myeong-Gie Kang(ANU) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Evaluation of a heat exchanger performance plugged in the RCP facility Hae-seob Choi(KAERI), Young-Jung Youn(KAERI), Jong-Kuk Park(KAERI), Seok Kim(KAERI), and Seok Cho(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Sensitivity analysis of condensation and air natural convection coefficients of air-cooled condensing heat exchanger of emergency cooldown tank in long-term passive cooling system Seon Jeong Huh(KMU), Joo Hyung Moon(KAERI), Youngmin Bae(KAERI), Young In Kim(KAERI), and Hee Joon Lee(KMU) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Prospect for seal performance test of the localized APR1400's RCP Seok CHO(KAERI), Seok KIM(KAERI), Byoung-Uhn BAE(KAERI), Yun-Jae CHO(KAERI), Yeon-SIK KIM(KAERI), Woo-Jin Jeon(KAERI), and Young-Jung Yun(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Integral Effect Test on 17% Cold Leg IBLOCA for Investigation of Scaling Effect Byoung-Uhn Bae(KAERI), Kyoung-Ho Kang(KAERI), Yu-Sun Park(KAERI), Jong-Rok Kim(KAERI), Hyung-Gil Jun(KAERI), Nam-Hyun Choi(KAERI), and Ki-Yong Choi(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) An Experimental Study of Droplet Entrainment in the Horizontal Stratified Flow Byeonggeon Bae(PNU), Jaejun Jeong(PNU), and Byongjo Yun(PNU) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Design of the down-scaled test vessel for a hydrodynamic simulation reflecting recent specification of PGSFR Seok-Kyu Chang(KAERI), Woo Shik Kim(KAERI), and Dong-Jin Euh(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Strategy development of the experimental characterization for mixing characteristics inside reactor vessel for reactor transient condition Dongjin Euh, Ki-Hwan Kim, and Tae-Soon Kwon(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Experimental Validation for Heat Removal Rate of Single Fin-Tube Heat Exchanger Kihwan Kim(KAERI), Kil-won Park(KAERI), and Tae-soon Kwon(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) An investigation on the effect of break location on the thermal-hydraulic characteristics of the SMART-ITL Jaemin Kim(KAERI), Myoung Jun Kim(KAERI), Hwang Bae(KAERI), Sung Uk Ryu(KAERI), Byoung-Guk Jeon(KAERI), Jin-Hwa Yang(KAERI), Eun-Koo Yoon(KAERI), Yong-Cheol Shin(KAERI), Kyoung-Ho Min(KAERI), Jong-Kuk PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Design and Simulation?for a Helical-coil Steam Generator?of?FINCLS Facility Eunkoo Yun(KAERI), Hwang Bae(KAERI), Sung-Uk Ryu(KAERI), Byong-Guk Jeon(KAERI), Jin-Hwa Yang(KAERI), Sung-Jae Yi(KAERI), and Hyun-Sik Park(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Introduction of the ATLAS Test Facility Upgrade Yusun Park(KAERI), Byoung-Uhn Bae(KAERI), Jongrok Kim(KAERI), Hyung-Gil Jun(KAERI), Young-Chul Shin(KAERI), Kyoung-Ho Min(KAERI), Nam-Hyun Choi(KAERI), Kyoung-Ho Kang(KAERI), and Ki-yong Choi(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) Experiments on Reflood with Deformed Fuel Rods during SB-MB LOCA in PWR SeungHyun Hong, Jong-Kuk Park, Young-Jung Youn, Hae Seob Choi, Sang-Ki Moon(KAERI) PDF보기 -
2017-Spring 5M : 원자력열수력 및 안전 (Thermal Hydraulics and Safety) 5.18(Thu) 13:00 로비 (3F) CFD Analysis for Verification of SFR Reactor Flow Distribution Test Facility Woo Shik Kim(KAERI), Seok-Kyu Chang(KAERI), and Dong-Jin Euh(KAERI) PDF보기 -
Last Modified : 1998-Autumn