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학술발표회 논문집

Year Div Date/Time ROOM Title Author Abstract File Presentation File
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) The Effect of Random Displacement in Spent Nuclear Fuel Cask Criticality Safety Analysis Seok Geun Cho, Keon Il Cha, and Kyoon Ho Cha(Sejong Univ.) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) Criticality Possibility Study in the Event of an Accident While Transporting Spent Nuclear Fuel Container KiHo Park, Keonil Cha, Nakwoong Yang, and Chang Je Park(Sejong Univ.) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) Sensitivity Study on Plutonium Production Potential from 5MWe YongByon Reactor Using McCARD Simulation Hyoeun LEE and Jaehyun CHO(CAU), Eunhyun RYU(KAERI), Yonhong JEONG(KINAC) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) Feasibility Study for Spent Fuel Pool Storage of LEU+ fuel JINHO JEONG(KHNP) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) Analysis of Axial Shape Index and Peaking Factors Considering Flexible Operation for Boron-Free i-SMR Core Seunghwan Jun(HYU|KEPCO NF), Bum Hee Jo(KEPCO NF), Ser Gi Hong(HYU) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) Preliminary Core Design with Internal Structure for Small-Sized Molten Salt Fast Reactor Seong Jun Yoon, Sung-Kyun Zee, Tongkyu Park, and Yubin Go(FNC Tech.) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) A Study of Long-term Cycle and Sensitivity Evaluation with NaCl-KCl-UCl3 Fueled MSR Core Design Yubin Go, Seong Jun Yoon, Tongkyu Park, and Sung-Kyun Zee(FNC Tech.) PDF보기 -
2024-Spring 2D : 원자로물리 및 계산과학 (Reactor Physics and Computational Science) 5.9(Thu) 13:00 Lobby (3F) The Identification of Chemical form of Fission Products Released in the Operation of 100Mw Chloride based Molten Salt Reactor(MSR) using FactSage Modeling JuHo Lee and ChangHwa Lee(KAERI) PDF보기 -
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 13:30 401A (4F) Efficient Inorganic 14C Removal using Ettringite from Waste Solution Bhupendra Kumar Singh, Nurul Syiffa Mahzan, and Wooyong Um(POSTECH) PDF보기 PPT보기
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 13:50 401A (4F) Development of Multi-element Hollandite Ceramic for Immobilizing Radioactive Cesium Using Active Learning Based on Bayesian Optimization Hyun Woo Seong, Ho Jin Yoon, and Ho Jin Ryu(KAIST) PDF보기 -
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 14:10 401A (4F) Preliminary Study of Exploring the Multi-elements Layered Double Hydroxides for Iodate Decontamination by Machine Learning Sujeong Lee, Tien-Shee Chee, and Ho Jin Ryu(KAIST), Juhwan Noh(KRICT) PDF보기 -
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 14:30 401A (4F) A Theoretical Study on the Half-life of Bound-State Beta Decay of Long-Lived Fission Products Konstantinos Volanis, Sunjoo Yoon, and Yonghee Kim(KAIST), David Mascali, Angelo Pidatella, and Bharat Mishra(INFN) PDF보기 -
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 14:50 401A (4F) Application of Fuzzy TOPSIS in Selecting Cutting Technology for Radioactive Waste Metal Melting Facility Hyunjin Boo, Su Hyeon Lee, and Byung Gi Park(SoonChunHyang Univ.) PDF보기 -
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 15:10 401A (4F) Sorption and Diffusion of Non-radioactive Isotopes under Oxidizing Disposal Environments Hyojoo Kim, Jaeeun Kang, and Wooyong Um(POSTECH), Jae-Kwang Lee and Jang-Soon Kwon(KAERI) PDF보기 PPT보기
2024-Spring 3A : 원자력시설해체 및 방사성폐기물관리 (Nuclear Facility Decommissioning and Radioactive Waste Management) 5.9(Thu) 15:30 401A (4F) Comparative Study of Thermodynamic Database (TDB) for Estimation of Radionuclide Solubility in KURT Conditions Jueun Kim, Kyungwon Kim, and Wooyong Um(POSTECH), Hye-Ryun Cho, Hee-Kyung Kim, Wansik Cha(KAERI) PDF보기 -
Last Modified : 1998-Autumn