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Abdallah A. Nahla (ORCID:0000-0003-3572-4167)
Abdallah A. Nahla (ORCID:0000-0003-3572-4167)
Other namesA. A. Nahla
Mathematics Department, Faculty of Science, Tanta University, Egypt & Taibah University, KSA
Verified email at science.tanta.edu.eg - Homepage
Title
Cited by
Cited by
Year
Solution of the point kinetics equations in the presence of Newtonian temperature feedback by Padé approximations via the analytical inversion method
AE Aboanber, AA Nahla
Journal of Physics A: Mathematical and General 35 (45), 9609, 2002
732002
Generalization of the analytical inversion method for the solution of the point kinetics equations
AE Aboanber, AA Nahla
Journal of Physics A: Mathematical and General 35 (14), 3245, 2002
682002
Taylor’s series method for solving the nonlinear point kinetics equations
AA Nahla
Nuclear Engineering and Design 241 (5), 1592-1595, 2011
612011
Analytical solution to solve the point reactor kinetics equations
AA Nahla
Nuclear Engineering and Design 240 (6), 1622-1629, 2010
602010
An efficient technique for the point reactor kinetics equations with Newtonian temperature feedback effects
AA Nahla
Annals of Nuclear Energy 38 (12), 2810-2817, 2011
532011
On pade′ approximations to the exponential function and application to the point kinetics equations
AE Aboanber, AA Nahla
Progress in Nuclear Energy 44 (4), 347-368, 2004
512004
Adaptive matrix formation (AMF) method of space–time multigroup reactor kinetics equations in multidimensional model
AE Aboanber, AA Nahla
Annals of Nuclear Energy 34 (1-2), 103-119, 2007
412007
An analytical solution for the point reactor kinetics equations with one group of delayed neutrons and the adiabatic feedback model
AA Nahla
Progress in Nuclear Energy 51 (1), 124-128, 2009
402009
Generalization of the analytical exponential model to solve the point kinetics equations of Be-and D2O-moderated reactors
AA Nahla
Nuclear Engineering and Design 238 (10), 2648-2653, 2008
392008
Solution of the nonlinear point nuclear reactor kinetics equations
AA Nahla, EME Zayed
Progress in Nuclear Energy 52 (8), 743-746, 2010
382010
Solution of two-dimensional space–time multigroup reactor kinetics equations by generalized Padé and cut-product approximations
AE Aboanber, AA Nahla
Annals of Nuclear Energy 33 (3), 209-222, 2006
312006
Numerical Techniques for the Neutron Diffusion Equations in the Nuclear Reactors
AA Nahla, FA Al-Malki, M Rokaya
Advanced Studies in Theoretical Physics 6 (14), 649 - 664, 2012
302012
Analytical exponential model for stochastic point kinetics equations via eigenvalues and eigenvectors
AA Nahla, AM Edress
Nuclear Science and Techniques 27, 1-8, 2016
212016
Efficient computational system for transient neutron diffusion model via finite difference and theta methods
AA Nahla
Annals of Nuclear Energy 89, 28-37, 2016
202016
Analytical solution of the fractional point kinetics equations with multi-group of delayed neutrons during start-up of a nuclear reactor
AA Nahla
Annals of Nuclear Energy 99, 247-252, 2017
192017
Numerical treatment for the point reactor kinetics equations using theta method, eigenvalues and eigenvectors
AA Nahla
Progress in Nuclear Energy 85, 756–763, 2015
192015
A novel fractional technique for the modified point kinetics equations
AE Aboanber, AA Nahla
Journal of the Egyptian Mathematical Society 24 (4), 666-671, 2016
182016
Efficient stochastic model for the point kinetics equations
AA Nahla, AM Edress
STOCHASTIC ANALYSIS AND APPLICATIONS 34 (4), 598-609, 2016
182016
A novel mathematical model for two-energy groups of the point kinetics reactor dynamics
AE Aboanber, AA Nahla, ZI Al-Muhiameed
Progress in Nuclear Energy 77 (November 2014), 160-166, 2014
162014
Picard iteration and Padé approximations for stiff fractional point kinetics equations
AA Nahla, AA Hemeda
Applied Mathematics and Computation 293, 72-80, 2017
152017
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