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 | 73 | 2002 |
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 | 68 | 2002 |
Taylor’s series method for solving the nonlinear point kinetics equations AA Nahla Nuclear Engineering and Design 241 (5), 1592-1595, 2011 | 61 | 2011 |
Analytical solution to solve the point reactor kinetics equations AA Nahla Nuclear Engineering and Design 240 (6), 1622-1629, 2010 | 60 | 2010 |
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 | 53 | 2011 |
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 | 51 | 2004 |
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 | 41 | 2007 |
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 | 40 | 2009 |
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 | 39 | 2008 |
Solution of the nonlinear point nuclear reactor kinetics equations AA Nahla, EME Zayed Progress in Nuclear Energy 52 (8), 743-746, 2010 | 38 | 2010 |
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 | 31 | 2006 |
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 | 30 | 2012 |
Analytical exponential model for stochastic point kinetics equations via eigenvalues and eigenvectors AA Nahla, AM Edress Nuclear Science and Techniques 27, 1-8, 2016 | 21 | 2016 |
Efficient computational system for transient neutron diffusion model via finite difference and theta methods AA Nahla Annals of Nuclear Energy 89, 28-37, 2016 | 20 | 2016 |
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 | 19 | 2017 |
Numerical treatment for the point reactor kinetics equations using theta method, eigenvalues and eigenvectors AA Nahla Progress in Nuclear Energy 85, 756–763, 2015 | 19 | 2015 |
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 | 18 | 2016 |
Efficient stochastic model for the point kinetics equations AA Nahla, AM Edress STOCHASTIC ANALYSIS AND APPLICATIONS 34 (4), 598-609, 2016 | 18 | 2016 |
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 | 16 | 2014 |
Picard iteration and Padé approximations for stiff fractional point kinetics equations AA Nahla, AA Hemeda Applied Mathematics and Computation 293, 72-80, 2017 | 15 | 2017 |