Nuclear Engineering and Design

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Sắp xếp:  
Minimization of the effect of errors in approximate radiation view factors
Nuclear Engineering and Design - Tập 149 - Trang 431-440 - 1994
Randy Clarksean, Charles Solbrig
Neutronic design of a sub-critical, source driven reactor at the RA-8 facility
Nuclear Engineering and Design - Tập 240 - Trang 771-775 - 2010
A. Cintas, J.I. Márquez Damián, E.M. Lopasso
A new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code
Nuclear Engineering and Design - Tập 373 - Trang 111009 - 2021
Mauricio E. Cazado, Ezequiel Goldberg, Martín A. Togneri, Alicia Denis, Alejandro Soba
New module for simulating experiments without irradiation included in the DIONISIO 3.0 code
Nuclear Engineering and Design - Tập 374 - Trang 111067 - 2021
Ezequiel Goldberg, Mauricio E. Cazado, Matías E. Loza Peralta, Alejandro Soba
A simple model for predicting energy dissipation of thin plates being perforated by “hard” missiles
Nuclear Engineering and Design - Tập 51 - Trang 157-161 - 1979
Ernst Limberger
Assessment of the integrated mass conservative Kalman filter algorithm for Computational Thermo-Fluid Dynamics on the TRIGA Mark II reactor
Nuclear Engineering and Design - Tập 384 - Trang 111431 - 2021
Carolina Introini, Davide Chiesa, Stefano Lorenzi, Massimiliano Nastasi, Ezio Previtali, Andrea Salvini, Monica Sisti, Luka Snoj, Antonio Cammi
Microstructural changes and fracture behavior of CF8M duplex stainless steels after long-term aging
Nuclear Engineering and Design - Tập 174 Số 3 - Trang 273-285 - 1997
Seiichi Kawaguchi, Naruo Sakamoto, Genta Takano, Fukuhisa Matsuda, Yasushi Kikuchi, Ľuboš Mráz
Convective boundary layer flow and heat transfer in a nanofluid in the presence of second order slip, constant heat flux and zero nanoparticles flux
Nuclear Engineering and Design - Tập 297 - Trang 95-103 - 2016
M.M. Rahman, Maryam H. Al-Rashdi, I. Pop
Axial crack propagation in fuel pin cladding tubes
Nuclear Engineering and Design - Tập 136 - Trang 243-254 - 1992
I.J. Ford
On the geometry of the fuel rod supports concerning a fretting wear failure
Nuclear Engineering and Design - Tập 238 Số 12 - Trang 3321-3330 - 2008
Hyung-Kyu Kim, Young-Ho Lee, Kanghee Lee
Tổng số: 7,323   
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