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No Journal_name Subject Date DOI Author
745958 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Signal processing method of bubble detection in sodium flow based on inverse Fourier transform to calculate energy ratio 2021-09-25 10.1016/j.net.2021.03.025 Xu, Wei, Xu, Ke-Jun, Yu, Xin-Long, Huang, Ya, Wu, Wen-Kai
745957 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Evaluation of 475 ℃ embrittlement in UNS S32750 super duplex stainless steel using four-point electric conductivity measurements 2021-09-25 10.1016/j.net.2021.03.018 Gutierrez-Vargas, Gildardo, Ruiz, Alberto, Lopez-Morelos, Victor H., Kim, Jin-Yeon, Gonzalez-Sanchez, Jorge, Medina-Flores, Ariosto
745956 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY A design of transmission-type multi-target X-ray tube based on electric field modulation 2021-09-25 10.1016/j.net.2021.03.002 Zhao, Lei, Jia, Wenbao, Jin, Limin, Shan, Qing, Cheng, Can, Zhu, Hongkui, Hei, Daqian
745955 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Review of researches on coupled system and CFD codes 2021-09-25 10.1016/j.net.2021.03.027 Long, Jianping, Zhang, Bin, Yang, Bao-Wen, Wang, Sipeng
745954 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Damage and vibrations of nuclear power plant buildings subjected to aircraft crash part II: Numerical simulations 2021-09-25 10.1016/j.net.2021.03.008 Li, Z.R., Li, Z.C., Dong, Z.F., Huang, T., Lu, Y.G., Rong, J.L., Wu, H.
745953 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Uncertainty analyses of spent nuclear fuel decay heat calculations using SCALE modules 2021-09-25 10.1016/j.net.2021.03.013 Shama, Ahmed, Rochman, Dimitri, Pudollek, Susanne, Caruso, Stefano, Pautz, Andreas
745952 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Simulation of low-enriched uranium burnup in Russian VVER-1000 reactors with the Serpent Monte-Carlo code 2021-09-25 10.1016/j.net.2021.03.014 Mercatali, L., Beydogan, N., Sanchez-Espinoza, V.H.
745951 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY A preliminary study on material effects of critical heat flux for downward-facing flow boiling 2021-09-25 10.1016/j.net.2021.03.024 Wang, Kai, Li, Chun-Yen, Uesugi, Kotaro, Erkan, Nejdet, Okamoto, Koji
745950 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY CFD analysis of the flow blockage in a rectangular fuel assembly of the IAEA 10 MW MTR research reactor 2021-09-25 10.1016/j.net.2021.03.028 Xia, Shuang, Zhou, Xuhua, Hu, Gaojie, Cao, Xiaxin
745949 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Experimental study of sodium fire and its characteristics under the coupling action of columnar liquid sodium flow and concrete 2021-09-25 10.1016/j.net.2021.03.011 Huo, Yan, Zou, Gao-Wan, Dong, Hui, Lv, Jian-Fu, He, Jian