Nuclear Engineering and Technology

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Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors
Nuclear Engineering and Technology - Tập 49 - Trang 1109-1112 - 2017
Ji-Hyun Yoon, Bong-Sang Lee
SrAl2Si2O8 ceramic matrices for 90Sr immobilization obtained via spark plasma sintering-reactive synthesis
Nuclear Engineering and Technology - Tập 53 - Trang 2289-2294 - 2021
E.K. Papynov, A.A. Belov, O.O. Shichalin, I. Yu Buravlev, S.A. Azon, A.V. Golub, A.V. Gerasimenko, Yu. А. Parotkina, A.P. Zavjalov, I.G. Tananaev, V.I. Sergienko
Prediction of golden time for recovering SISs using deep fuzzy neural networks with rule-dropout
Nuclear Engineering and Technology - Tập 53 - Trang 4014-4021 - 2021
Hye Seon Jo, Young Do Koo, Ji Hun Park, Sang Won Oh, Chang-Hwoi Kim, Man Gyun Na
Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes
Nuclear Engineering and Technology - Tập 50 - Trang 425-431 - 2018
Márton Király, Dániel Mihály Antók, Lászlóné Horváth, Zoltán Hózer
Imbalanced sample fault diagnosis method for rotating machinery in nuclear power plants based on deep convolutional conditional generative adversarial network
Nuclear Engineering and Technology - Tập 55 - Trang 2096-2106 - 2023
Zhichao Wang, Hong Xia, Jiyu Zhang, Bo Yang, Wenzhe Yin
OECD/NEA BENCHMARK FOR UNCERTAINTY ANALYSIS IN MODELING (UAM) FOR LWRS – SUMMARY AND DISCUSSION OF NEUTRONICS CASES (PHASE I)
Nuclear Engineering and Technology - Tập 46 - Trang 313-342 - 2014
RYAN N. BRATTON, M. AVRAMOVA, K. IVANOV
An ultra-long-life small safe fast reactor core concept having heterogeneous driver-blanket fuel assemblies
Nuclear Engineering and Technology - Tập 53 - Trang 3517-3527 - 2021
Kyu Jung Choi, Yeonguk Jo, Ser Gi Hong
First Studies for the Development of Computational Tools for the Design of Liquid Metal Electromagnetic Pumps
Nuclear Engineering and Technology - Tập 49 - Trang 82-91 - 2017
Carlos O. Maidana, Juha E. Nieminen
Study on multi-objective optimization method for radiation shield design of nuclear reactors
Nuclear Engineering and Technology - - 2023
Yao Wu, Bin Liu, Xiaowei Su, Songqian Tang, Mingfei Yan, Liangming Pan
SAFETY ANALYSIS METHODOLOGY FOR AGED CANDU® 6 NUCLEAR REACTORS
Nuclear Engineering and Technology - Tập 45 - Trang 581-588 - 2013
WOLFGANG HARTMANN, JONG YEOB JUNG
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