학술정보출판물

한국원자력학회에 오신 것을 환영합니다.

학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2023-Spring 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.18(Thu) 13:00 Lobby (3F) The Need for Performance Evaluation prior to Direct Use of Commercial Resin JUNG BO YOO and HYO JIN AHN(KAERI) PDF보기 -
2023-Spring 3D : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.18(Thu) 13:00 Lobby (3F) A Study on Assessment System for the Integrity of Spent Nuclear Fuel under Normal Conditions of Transport Woo-seok Choi, JaeHoon Lim, Jongmin Lim, and Gil-Eon Jeong(KAERI) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:00 202B (2F) Post-quench Ductility of Cr-coated (8μm, AIP) Zr-1.1Nb Accident Tolerant Fuel Cladding and Accident Margin Analysis SungHoon Joung and Youho Lee(SNU) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:20 202B (2F) Thermo-mechanical Analysis of Multi-layered Accident-tolerant fuel (ATF) Claddings Jiwon Mun, Hyeong-Jin Kim, and Ho Jin Ryu(KAIST) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:40 202B (2F) Numerical Investigation of Creep Behavior of Cr-coated ATF under Steady-state Condition Jinsu Kim, Hyuntaek Rho, and Youho Lee(SNU) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 10:00 202B (2F) 2D FDM Structural Analysis Model for Cr-coated ATF Cladding: Development and Implementation into Fuel Analysis Code Hyuntaek Rho and Youho Lee(SNU) PDF보기 PPT보기
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 10:20 202B (2F) Development and Evaluation of Cold Spray Cr-coated Zr-alloy Cladding as Accident Tolerant Fuel (ATF) Design in LWRs Hwasung Yeom(POSTECH), Kumar Sridharan(University of Wisconsin-Madison) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 11:00 202B (2F) Effects of Acoustic Impedance on Spent Nuclear Fuel Ultrasonic Inspection Kyung Gun Kim and Jin Ho Jeong(KHNP) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 11:20 202B (2F) Exploring the Microstructural Difference Between Circumferential Hydride and Radial Hydride in Reactor-grade Zirconium Cladding Tube Dahyeon Woo and Youho Lee(SNU), Joo-Hee Kang(KIMS) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 11:40 202B (2F) Effect of Reduced Hydride Connectivity on the Mechanical Strength of Zircaloy Via Grain Growth Sangbum Kim and Youho Lee(SNU) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 12:00 202B (2F) A Comparative Study on Spent Nuclear Fuels under Normal and Postulated Conditions of Transportation Min Jeong Park, Yong Gyun Shin, and Yoon-Suk Chang(KHU) PDF보기 -
2023-Spring 4A : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 12:20 202B (2F) Electron Irradiated ZrC layer in Surrogate TRISO Fuel Particles Sunghwan Yeo, Hyunggen Lee, Eungsun Kim, and Jun Hwan Kim(KAERI) PDF보기 -
2023-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:00 203 (2F) On the Wrong Use of Sodium Hydroxide as a Chemical Impurity Concentrated in Nuclear Steam Generator Crevices Do Haeng Hur, Jeoh Han, and Soon-Hyeok Jeon(KAERI), Geun-Dong Song(FNC Tech.) PDF보기 -
2023-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:20 203 (2F) Atomistic Investigation of Interstitial Dislocation Loop Formation and Threshold Displacement Energy in Tantalum and Tantalum-Tungsten Alloy by Low Temperature Irradiation under Local Deformation Mohammad Banisalman, Minkyu Park, and Mosab Banisalman(Virtual Lab Inc.) PDF보기 -
2023-Spring 4B : 핵연료 및 원자력재료 (Nuclear Fuel and Materials) 5.18(Thu) 09:40 203 (2F) Multiscale Modeling Approach to Hygroelastic Aging of Epoxy and Epoxy Nanocomposites Seunghwa Yang and Inseok Jeon(CAU), Seonyong Kwon(Samyang Corp) PDF보기 -
Last Modified : 1998-Autumn