학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Experimental Study of Condensation Heat Transfer and Droplet Dynamic on Multiple Horizontal Copper Tubes with Super hydrophobic Characteristic Hyunjun Sun and Kwon-Yeong Lee(HGU) PDF보기 PPT보기
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) High-fidelity Imaging of Subcooled Flow Boiling using Synchrotron X-ray and Laser Interferometry Haeram Jeong, Sieun Kim, and Hyungdae Kim(KHU) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Design of High-Pressure Flow Boiling Experimental Apparatus Applicable for Integrated Visualizations of Boiling Heat Transfer and Bubble Dynamics Junha Kang, Donggyun Seo, and Hyungdae Kim(KHU) PDF보기 PPT보기
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Experimental Investigation of Thermal Hydraulic Characteristic of Water Based Thermosyphon under Evacuated Non-condensable and Pressurized Non-condensable Benrico Fredi Simamora and Jae Young Lee(HGU) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Experimental Study of Two-phase Pressure Drop of Corrugated Mini Channel Bowon Hwang, Haeun Noh, and Jaeyoung Lee(HGU) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Analysis of Heat Transfer Performance in Two-Phase Closed Thermosyphon Applied Superhydrophilic and Superhydrophobic Surface Modification Seong-Won Seo, Hyukjun Ha, and Kwon-Young Lee(HGU) PDF보기 -
2023-Spring 5G : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) A Modeling of Supercritical CO2 Brayton Cycle for a Small Modular Molten Salt Reactor on Nuclear-powered\nShip Wonkoo Lee, Chan-Yong Lee, and Kwon-Yeong Lee(HGU) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Proposed Improvement of Existing SBLOCA M/E Analysis Methodology BUMSOO YOUN, DONGHYUK LEE, and KYUNGHO NAM(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Analyses of Turbulence Induced Vibration on Trim Shapes of Control Valve with High Pressure Drop Sangyun Je, Hyuksoon Lee, Taekyung Lee, and Ji-woong Bae(KHNP), Hoon Jang(Total Engineering Soulution) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) GAMMA+ Code Verification for Natural Circulation Phenomena in a MSR System SUNG NAM Lee, Nam-il Tak, Hong-Sik Lim, and Sang Ji Kim(KAERI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Simulation of a Linear Quadratic Regulator Controller for sCO2 Cycle Using MARS-KS Gi Hyeon Kim and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Simulation of IBLOCA (Intermediate-break Loss of a Coolant Accident) Scenario of PKL i2.2 Test Jong Hyuk Lee and Seung Wook Lee(KAERI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Evaluation of the Increase in Feedwater Accident with Common Cause Failure during Flexible Operation using SPACE Code Hyoung Kyoun Ahn, In Ho Song, and Seok Jeong Park(KEPCO E&C), Lee Jae Min(KHNP CRI) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Study on Main Steam Line Break Induced Steam Generator Tube Rupture Accident using SPACE Code MinJeong Kim, Chang-Keun Yang, and Seung-Chan LEE(KHNP) PDF보기 -
2023-Spring 5H : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:00 Lobby (3F) Sensitivity Test for Intermediate Break Loss of Coolant of LSTF No.2 using SPACE Chiwoong CHOI, Byung-hyun Yoo, and Seung-wook Lee(KAERI) PDF보기 -
Last Modified : 1998-Autumn