Nuclear Engineering and Design
Công bố khoa học tiêu biểu
* Dữ liệu chỉ mang tính chất tham khảo
Sắp xếp:
Minimization of the effect of errors in approximate radiation view factors
Nuclear Engineering and Design - Tập 149 - Trang 431-440 - 1994
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 new irradiation growth model for Zr-based components of nuclear reactors for the DIONISIO code
Nuclear Engineering and Design - Tập 373 - Trang 111009 - 2021
New module for simulating experiments without irradiation included in the DIONISIO 3.0 code
Nuclear Engineering and Design - Tập 374 - Trang 111067 - 2021
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
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
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
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
Axial crack propagation in fuel pin cladding tubes
Nuclear Engineering and Design - Tập 136 - Trang 243-254 - 1992
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
Tổng số: 7,323
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