Nuclear Engineering and Design

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The effect of coupled wear and creep during grid-to-rod fretting
Nuclear Engineering and Design - Tập 318 - Trang 163-173 - 2017
Hai Wang, Zupan Hu, Wei Lu, M.D. Thouless
On the theory of the gamma-ray transmission, dual-distance principle of determining thickness
Nuclear Engineering and Design - Tập 15 - Trang 237-240 - 1971
R.L. Ely
Behavior of surface crack in plates subjected to tensile loads: Analysis based on fully plastic solutions
Nuclear Engineering and Design - Tập 111 - Trang 189-196 - 1989
G. Yagawa, H. Ueda
Modelling flow and work hardening behaviour of cold worked Zr–2.5Nb pressure tube material in the temperature range of 30–600̊C
Nuclear Engineering and Design - Tập 269 - Trang 52-56 - 2014
A.K. Dureja, S.K. Sinha, D.N. Pawaskar, P. Seshu, J.K. Chakravartty, R.K. Sinha
Dynamic response analysis for fuel assemblies under earthquake and LOCA accidents
Nuclear Engineering and Design - Tập 228 - Trang 15-20 - 2004
Xie Yongcheng, Yao Weida, Jiang Nanyan, Shi Guolin, Yang Renan
Advanced benchmark of the flow through a mixing vane grid – Large eddy simulation validation
Nuclear Engineering and Design - Tập 381 - Trang 111335 - 2021
Benjamin Farges, Marie-Charlotte Gauffre, Sofiane Benhamadouche, Pierre Badel, Vincent Faucher, Guillaume Ricciardi
Experimental and numerical determination of the rate of mass loss and temperature evolution of the single fuel rod cladding imitator during its melting
Nuclear Engineering and Design - Tập 363 - Trang 110681 - 2020
P.D. Lobanov, V.S. Zhdanov, E.V. Usov, A.I. Svetonosov, I.A. Klimonov
A network method for homogeneous, thermally expandable two-phase flow on unstructured triangular grids
Nuclear Engineering and Design - Tập 146 - Trang 473-481 - 1994
T.A. Porsching, C.A. Hall
A multi-scale and multi-physics simulation methodology with the state-of-the-art tools for safety analysis in Light Water Reactors applied to a Turbine Trip scenario (Part II)
Nuclear Engineering and Design - Tập 350 - Trang 205-213 - 2019
Patricio Hidalga, Agustín Abarca, Rafael Miró, Abdelkrim Sekrhi, Gumersindo Verdú
A fault diagnosis method based on signed directed graph and matrix for nuclear power plants
Nuclear Engineering and Design - Tập 297 - Trang 166-174 - 2016
Yong-Kuo Liu, Guo-Hua Wu, Chun-Li Xie, Zhi-Yong Duan, Min-Jun Peng, Meng-Kun Li
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