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No Journal_name Subject Date DOI Author
669168 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Model of the onset of liquid entrainment in large branch T-junction with the consideration of surface tension 2021-03-25 10.1016/j.net.2020.09.002 Liu, Ping, Shen, Geyu, Li, Xiaoyu, Gao, Jinchen, Meng, Zhaoming
669167 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Analysis of fission product reduction strategy in SGTR accident using CFVS 2021-03-25 10.1016/j.net.2020.08.003 Shin, Hoyoung, Kim, Seungwoo, Park, Yerim, Jin, Youngho, Kim, Dong Ha, Jae, Moosung
669166 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Perception-based analytical technique of evacuation behavior under radiological emergency: An illustration of the Kori area 2021-03-25 10.1016/j.net.2020.08.012 Kim, Jeongsik, Kim, Byoung-Jik, Kim, Namhun
669165 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY MPS eutectic reaction model development for severe accident phenomenon simulation 2021-03-25 10.1016/j.net.2020.08.018 Zhu, Yingzi, Xiong, Jinbiao, Yang, Yanhua
669164 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Applications of online simulation supporting PWR operations 2021-03-25 10.1016/j.net.2020.07.036 Wang, Chunbing, Duan, Qizhi, Zhang, Chao, Fan, Yipeng
669163 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters 2021-03-25 10.1016/j.net.2020.07.012 Ebiwonjumi, Bamidele, Kong, Chidong, Zhang, Peng, Cherezov, Alexey, Lee, Deokjung
669162 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Core analysis of accident tolerant fuel cladding for SMART reactor under normal operation and rod ejection accident using DRAGON and PARCS 2021-03-25 10.1016/j.net.2020.08.025 Pourrostam, A., Talebi, S., Safarzadeh, O.
669161 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Design of the flexible switching controller for small PWR core power control with the multi-model 2021-03-25 10.1016/j.net.2020.07.037 Zeng, Wenjie, Jiang, Qingfeng, Du, Shangmian, Hui, Tianyu, Liu, Yinuo, Li, Sha
669160 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Numerical simulation on LMR molten-core centralized sloshing benchmark experiment using multi-phase smoothed particle hydrodynamics 2021-03-25 10.1016/j.net.2020.07.039 Jo, Young Beom, Park, So-Hyun, Park, Juryong, Kim, Eung Soo
669159 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Quantification of predicted uncertainty for a data-based model 2021-03-25 10.1016/j.net.2020.08.002 Chai, Jangbom, Kim, Taeyun