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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Forced Core Flow Mixing Tests Tae-Soon Kwon, Dong-Jin Euh, and Ki-Hwan Kim(KAERI) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Reactor Flow and Structure Vibration Models Tae-Soon Kwon(KAERI) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Long-term Stability of OTS Coating Inducing Dropwise Condensation Heat Transfer Juhyeong Lee, HoJin Hwang, GoenHyeong Lee, Taeseok Kim, and Sung Joong Kim(HYU) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Particle Image Velocimetry Analysis using Deep Learning for Thermal-hydraulics Experiment Jun Sung Choi and Eung Soo Kim(SNU) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line The Effect of Sliding large Bubbles on Nucleate Boiling of Subcooled Water Fowing in a Slightly Inclined Channel Subjected to Upper Heated Surface Uiju Jeong(KHNP CRI), Sung Joong Kim(HYU) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Evaluation on Prediction Capability of GOTHIC Code for KAERI Single Tube Condensation Experiment Jae-Ho Bae, Yeon-Jun Choo, Hee-Dong Kim, and Soon-Joon Hong(FNC Tech.) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Design and Manufacture of Fouling Simulation Test Apparatus for a Printed Circuit Steam Generator Jeoh Han, Sang-Ji Kim, and Do Haeng Hur(KAERI), Young-Kook Lee(Yonsei Univ.) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Experimental Study of Dropwise Condensation on Various S.A.M Condenser Tubes Ha-Yeol Kim, Myeong-Chan Park, Su-Bin Jeong, and Kwon-Yeong Lee(HGU), Young-Hun Shin and Woonbong Hwang (POSTECH) PDF보기 -
2020-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Development of Measurement System for Thermo-mechanical Behavior of Cladding in LOCA-Simulated Experiments Hyeokjun Byeon, Jae Bong Lee, Jongrok Kim, Kihwan Kim, Hae Seop Choi, Jong-Kuk Park, Young-Jung Youn, and Sang-Ki Moon(KAERI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line CFD Simulation of Cavitation Flow Inside a Cavitating Venturi Using ANSYS CFX Gong Hee Lee and June Ho Bae(KINS) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line OPR1000 ATWS Analysis Using the SPACE Code Bum-Soo Youn and KYUNGHO NAM(KHNP CRI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Simulation of OECD/ATLAS A4.1 Test with TRACE Code Kyung Won Lee, Min Ki Cho, and Andong Shin(KINS) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Sensitivity Analysis of Heat Loss through Secondary System for MSGTR with PAFS Operation Tae-woo Kim and KYUNGHO NAM(KHNP CRI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line The Prediction Method of Entrainment Rate by Breakup of Large Drop During Reflood in a TH Code Seung Hyun Yoon, Kyung Doo Kim, Jaeseok Heo, and Kwiseok Ha(KAERI) PDF보기 -
2020-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 7.9(Thu)~7.10(Fri) On-line Application of Heat Transfer Enhancement Factors at Downstream of Quench Front Considering Collapsed Water Level Seung Hyun Yoon, Jaeseok Heo, Kyung Doo Kim, Chiwoong Choi, and Kwiseok Ha(KAERI) PDF보기 -
Last Modified : 1998-Autumn