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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Corrosion Behaviors of Ni-based Alloy in Molten NaCl-MgCl₂ salt with a Cyclic Temperature System Younghwan Jeon, Ugyu Jeong, Yeojin Kim, and Jaeyeong Park(UNIST) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Hydrothermal Corrosion Behaviors of Cr-Based Alloy and Nitride Coated Nuclear Fuel Cladding Jung Ho Shin and Sangha Park(DMI) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Investigation of Corrosion Control Technologies for Structural Materials in MSR Changhyun Shim, Younghwan Jeon, and Jaeyeong Park(UNIST) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Simulation Model of Molten Salt Corrosion Using COMSOL Maehyun Cho and Kunok Chang(KHU) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Investigating the Influence of Stress on Helium Bubble Formation and Swelling in RAFM Steel Sangeun Kim and Hyung-ha Jin(KAERI), Minkyu Ahn, Jinwoo Park, Gyeongsik Yu, and Chansun Shin(Myongji Univ.), Chang-Hoon Lee(KIMS) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Corrosion Behavior of Austenitic Stainless Steel Used in Nuclear Power Plant Cooling Water Component After Plasma Electrolytic Oxidation Jun Heo, Seunguk Cheon, and Sung Oh Cho(KAIST) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Development of Tools for Stress Calculations in Fluid-Structure Interaction Analysis using Open-source Codes: A Case Study on Fatigue Damage Assessment Jin Haeng Lee, Dehee Kim, and Jonggan Hong(KAERI) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Changes in Mechanical Properties of Candidate Structural Materials by Corrosion in High Temperature Molten Salt Ji-Hyun Yoon(KAERI) PDF보기 -
2023-Spring 4G : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 13:00 Lobby (3F) Development of Wear Prediction Model for Steam Generator Tubes Daeyeop Kwon and Chi Bum Bahn(PNU), Heejae Shin and Young-Jin Oh(KEPCO E&C) PDF보기 -
2023-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:30 302 (3F) Evaluation Performance of Spent Fuel Pool Cooling System with Water Jacket Heat Pipe Sanghoon Lee, Min Suk Lee, Wooseong Park, and Young Hoon Jeong(KAIST) PDF보기 -
2023-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 13:50 302 (3F) Design and Evaluation of a Hybrid Cesium Heat Pipe Shutdown Rod as a Passive Safety System for Microreactors Dong Hun Lee and In Cheol Bang(UNIST) PDF보기 -
2023-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:10 302 (3F) Preliminary Study on Effective Thermal Mass of Supercritical Carbon Dioxide Heat Exchanger In Woo Son, Gi Hyeon Kim, Seung Kyu Lee, and Jeong Ik Lee(KAIST) PDF보기 -
2023-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:30 302 (3F) Simultaneous Two-Axis Force and Displace Measurement Techniques for Vortex Shedding in SMART100 Heat Exchanger Tube Array Chan Lee, Dongseok Oh, Kanghee Lee, Suho Kim, and Heungseok Kang(KAERI) PDF보기 -
2023-Spring 5A : 원자력열수력 (Nuclear Thermal Hydraulics) 5.18(Thu) 14:50 302 (3F) Bended Zone Tube Assembly Vibration of Coiled Steam Generator Under Downward Flow Kang-Hee Lee, Heung-Soek Kang, Sung-Wuk Lee, and Tae-Hyun Chun(KAERI) PDF보기 -
2023-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:00 301 (3F) Analysis of SBLOCA for CRDM Nozzle Rupture with Loss of Safety Injection at the ATLAS Experimental Facility using the MARS-KS 1.5 and TRACE V5.0 Patch 6 Hyunjoon Jeong and Taewan Kim(INU) PDF보기 -
Last Modified : 1998-Autumn