학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

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) 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 -
2023-Spring 5B : 원자력열수력 (Nuclear Thermal Hydraulics) 5.19(Fri) 09:20 301 (3F) Experimental Study on the Main Steam Line Break (MSLB) Accidnet Accompanied by the Loss of Shutdown Cooling System(SCS) based on the Risk/Performance Information Yusun Park, Byoung Uhn Bae, Jong Rok Kim, Jae Bong Lee, Seok Cho, Nam Hyun Choi, and Kyoung Ho Kang(KAERI), Jae Beol Hong and Hyun Bin Chang(FNC Tech.) PDF보기 -
Last Modified : 1998-Autumn