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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2018-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 10:00 세미나3 (B1F) Flow Instability Inside Passive Containment Cooling System and Mitigation Strategies Kyung Mo Kim and In Cheol Bang(UNIST), Jae Yul Kim(KEPCO E&C) PDF보기 -
2018-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 10:20 세미나3 (B1F) Numerical Study for Complete Flow Blockages of Plate-type Fuel Assembly Jong-Pil Park(KAERI) PDF보기 -
2018-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 11:00 세미나3 (B1F) Improvement of Well-posedness of SPACE Code using the One-dimensional Turbulence Term Byoung Jae Kim and Young Seock An(CNU), and Kyung Doo Kim(KAERI) PDF보기 -
2018-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 11:20 세미나3 (B1F) Assessment Calculation of OECD-ATLAS B3.1 Surge Line Break Accident by using SPACE Code Sung Won Bae, Kyung Ho Kang, and Kyung Doo Kim(KAERI) - -
2018-Autumn 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 11:40 세미나3 (B1F) Thermal-Hydraulic Modeling and Sensitivity Analysis of Multiple Steam Generator Tube Rupture Event in Shin-Kori Units 1&2 Bongsik Chu and Minjeong Kim(KHNP CRI) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 09:00 세미나9 (B1F) Evaluation for the Impact of Uncertainty Parameters on PCT by the Linear Regression Analysis Byung Gil Huh, Deog-Yeon Oh, Il Suk Lee, and Chae-Yong Yang(KINS) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 09:20 세미나9 (B1F) Preliminary Analysis of LOFT LP-FW-1 Test using SPACE Code Chiwoong CHOI, Kwiseok Ha, Seung Wook Lee, and Kyungdoo Kim(KAERI) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 09:40 세미나9 (B1F) Two Fluid Equation Considering Time-dependent Change of Thermal-Hydraulic Volume Jong Hyuk Lee and Kyung Doo Kim(KAERI), Byoung Jae Kim(CNU) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 10:00 세미나9 (B1F) Study of Real Time Accident Initiator Tracking Algorithm for Small Modular Reactor ChoHwan Oh and Jeong Ik Lee(KAIST) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 10:20 세미나9 (B1F) Factors Affecting Fuel Rod Burst in LOCA Safety Analysis Joosuk Lee and Young-Seok Bang(KINS) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 11:00 세미나9 (B1F) Uncertainty Quantification for Multi-Scale Reflood Tests Using Neural Network Based Surrogate Models Hae Min Park, Jaeseok Heo, and Kyung Doo Kim(KAERI) PDF보기 -
2018-Autumn 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 10.25(Thu) 11:20 세미나9 (B1F) Modeling of Eddy Viscosity for Density-Varying Fluids Yoon-Yeong Bae, Eung-Seon Kim, and Minhwan Kim(KAERI) PDF보기 PPT보기
2018-Autumn 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 10.26(Fri) 09:00 세미나2 (B1F) PCM Heat Transfer Experiment with PureTemp58X Jai Oan Cho, Jaehyung Sim, and Jeong Ik Lee(KAIST) PDF보기 -
2018-Autumn 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 10.26(Fri) 09:20 세미나2 (B1F) An Experimental Study on the Condensation of Steam-air Mixture of a Vertical Single Tube Jaemin Lee, Sang-Gyu Lim, Sang-Won Lee, Jong Cheon, and Seung-Min Ohk(KHNP CRI) PDF보기 -
2018-Autumn 5C : 원자력열수력 (Nuclear Thermal Hydraulics) 10.26(Fri) 09:40 세미나2 (B1F) Experimental Investigation of the Tube Diameter Effect on the Condensation in the Steam-air Free Convection Condition Jinhoon Kang and Byongjo Yun(PNU), Sangkyu Im and Jong Cheon(KHNP CRI) PDF보기 -
Last Modified : 1998-Autumn