학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 09:40 On-line Development of an Advanced Cladding Mechanical Model and Its Application for Thermal Hydraulics Coupled Failure Analysis of SiC LWR Fuel Cladding during LBLOCA Hyuntaek Rho and Youho Lee(SNU) PDF보기 PPT보기
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 10:00 On-line Development of ATF Pellet with High Thermal Conductivity and Fission Gas Retention Capability Dong-Joo Kim, Keon Sik Kim, Dong Seok Kim, Yang-Hyun Koo, Ji-Hae Yoon, Jae Ho Yang, Heung Soo Lee, and Hyun-Gil Kim(KAERI), Kwang-Young Lim and Seung-Jae Lee(KEPCO NF) PDF보기 -
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 10:20 On-line Oxidation Behavior of UO₂-Mo Composite Pellets Jae Ho Yang, Dong-Joo Kim, Dong Seok Kim, Ji-Hae Yoon, and Heung Soo Lee(KAERI) PDF보기 -
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 10:40 On-line Effect of Steam on UO₂ Pellet Oxidation in Fuel Rod using Thermodynamic Calculation Taesik Jung, Yeonsoo Na, Minjae Joo, Kwangyoung Lim, Yoonho Kim, and Seungjae Lee(KEPCO NF) PDF보기 PPT보기
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 11:00 On-line Simulation of the High Burnup Structure of UO₂ under a Thermal Gradient using the Hybrid Phase-Field Potts Kinetic Monte Carlo Model Faris B. Sweidan and Ho Jin Ryu(KAIST) PDF보기 -
2020-Autumn 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 11:20 On-line Development of NEST Experimental Setup for Large Deformation Test of Cladding with Neighboring Rod Effect using DIC Techniques Jong-Dae Hong, Dong-Hyun Kim, Hongryul Oh, Gyeongha Choi, and Hyo-Chan Kim(KAERI) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 13:30 On-line Development of PWSCC Initiation Model for Alloy 182 Welds Considering Thermal Aging and Cold Work Effects Jae Phil Park and Chi Bum Bahn(PNU), Seung Chang Yoo and Ji Hyun Kim(UNIST) PDF보기 PPT보기
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 13:50 On-line Effect of Zinc Concentration on General Corrosion Behavior and Oxide Films of Alloy 690TT in Simulated PWR Primary Water Dong-Seok Lim, Soon-Hyeok Jeon, and Do Haeng Hur(KAERI), JongHyeon Lee(CNU), Jinsoo Choi and Kyu Min Song(KHNP CRI) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 14:10 On-line Cracking and Surface Oxidation Behavior of Proton-Irradiated Type 316 Stainless Steel in PWR Primary Water Yun Soo Lim, Seong Sik Hwang, Dong Jin Kim, Min Jae Choi, and Jong Yeon Lee(KAERI) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 14:30 On-line Oxidation Resistance Improvement Mechanism of Si in FeCrSi Alloy at High Temperature Steam Environment Joonho Moon, Sungyu Kim, and Chi Bum Bahn(PNU), Ji Hyun Kim(UNIST), Michael P. Short(MIT) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 14:50 On-line Corrosion Behavior of Fe-Cr-Al Alloys with Yttrium Addition on 360 ℃ Simulated Pressurized Water Chemistry Condition Taeyong Kim, Seung Chang Yoo, Junhyuk Ham, Yunju Lee, Song In Young, and Ji Hyun Kim(UNIST), Sungyu Kim and Chi Bum Bahn(PNU) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 15:10 On-line Chemistry Analysis of Crud in Fuel Cladding under Various Heat Flux Conditions Yunju Lee, Junhyuk Ham, Seung Chang Yoo, Dae Hyeon Park, and Ji Hyun Kim(UNIST) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 15:50 On-line Evaluation of Coating for Venturi Fouling Mitigation at Nuclear Power Plant Wonjun Choi and Chi Bum Bahn(PNU), Young-Jin Kim, Dong-Seok Lim, and Hyun-Chul Lee(FNC Tech.) PDF보기 -
2020-Autumn 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.17(Thu) 16:10 On-line Experimental Evaluation of TiN Coating on Fouling Resistance of PWR Fuel Cladding JUNHYUK HAM, YUNJU LEE, SEUNG CHANG YOO, and JI HYUN KIM(UNIST) PDF보기 -
2020-Autumn 4C : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 12.18(Fri) 09:00 On-line Preliminary Experimental Study of High Temperature Interaction between Uranium Nitride Pellet and Eutectic Lead-Bismuth Coolant Gyeonghun Kim and Sangjoon Ahn(UNIST) PDF보기 -
Last Modified : 1998-Autumn