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No Journal_name Subject Date DOI Author
787988 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARK 2022-01-01 Chen Zhao, Xingjie Peng, Hongbo Zhang, Wenbo Zhao, Qing Li, Zhang Chen
787987 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY FTIR study of gamma and electron irradiated high-density polyethylene for high dose measurements 2022-01-01 Hanan Al-Ghamdi, Khaled Farah, Aljawharah Almuqrin, Faouzi Hosni
787986 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY p Ignition and flame propagation in hydrogen-air layers from a geological nuclear waste repository: A preliminary study 2022-01-01 10.1016/j.net.2021.07.011 Ryu, Je Ir, Woo, Seung Min, Lee, Manseok, Yoon, Hyun Chul
787985 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Analysis of steam generator tube rupture accidents for the development of mitigation strategies 2022-01-01 10.1016/j.net.2021.07.032 Bang, Jungjin, Choi, Gi Hyeon, Jerng, Dong-Wook, Bae, Sung-Won, Jang, Sunghyon, Ha, Sang Jun
787984 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Analyses of hydrogen risk in containment filtered venting system using MELCOR 2022-01-01 10.1016/j.net.2021.07.046 Choi, Gi Hyeon, Jerng, Dong-Wook, Kim, Tae Woon
787983 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Analysis of pipe thickness reduction according to pH in FAC facility with In situ ultrasonic measurement real time monitoring 2022-01-01 10.1016/j.net.2021.07.048 Oh, Se-Beom, Kim, Jongbeom, Lee, Jong-Yeon, Kim, Dong-Jin, Kim, Kyung-Mo
787982 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Mechanical performance of additively manufactured austenitic 316L stainless steel 2022-01-01 10.1016/j.net.2021.07.041 Kim, Kyu-Tae
787981 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate 2022-01-01 10.1016/j.net.2021.07.037 Song, Min Seop, Park, Il Woong, Kim, Eung Soo, Lee, Yeon-Gun
787980 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Sensitivity analysis of input variables to establish fire damage thresholds for redundant electrical panels 2022-01-01 10.1016/j.net.2021.07.044 Kim, Byeongjun, Lee, Jaiho, Shin, Weon Gyu
787979 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY How to incorporate human failure event recovery into minimal cut set generation stage for efficient probabilistic safety assessments of nuclear power plants 2022-01-01 10.1016/j.net.2021.04.026 Jung, Woo Sik, Park, Seong Kyu, Weglian, John E., Riley, Jeff