This work focuses on the k-eigenvalue problem of the neutron transport equation. The variables of interest are the largest eigenvalue (keff) and the corresponding eigenmode is called the fundamental mode. Mathematically, this problem is usually solved using the power iteration method. However, the convergence of this algorithm can be very slow, especially if the dominance ratio is high as is the case in some reactor physics applications. Thus, the power iteration method has to be accelerated in some ways to improve its convergence. One such acceleration is the Chebyshev acceleration method which has been widely applied to legacy codes. In recent years, nonlinear methods have been applied to solve the k-eigenvalue problem. Nevertheless, they...
The study of the steady-state solutions of neutron transport equation requires the introduction of a...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
An accelerated numerical method is developed for one-speed one-dimensional neutron transport eigenva...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
The instability problem of the modified power method was studied. The modified power iteration metho...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
Computing effective eigenvalues for neutron transport often requires a fine numerical resolution. Th...
The Iterative Quasi-Monte Carlo method, or iQMC, replaces standard quadrature techniques used in det...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2006Thesis (Ph.D.) -- İstanbul Tech...
Using certain well-known properties of chebyshev polynomials, a simple and highly efficient approach...
The study of the steady-state solutions of neutron transport equation requires the introduction of a...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
An accelerated numerical method is developed for one-speed one-dimensional neutron transport eigenva...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
International audienceThis work investigates the solution of the multigroup neutron transport equati...
International audienceThe simulation of the neutron transport inside a nuclear reactor leads to the ...
The instability problem of the modified power method was studied. The modified power iteration metho...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
Computing effective eigenvalues for neutron transport often requires a fine numerical resolution. Th...
The Iterative Quasi-Monte Carlo method, or iQMC, replaces standard quadrature techniques used in det...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
Time-dependent neutron transport in non-critical state can be expressed by the natural mode equation...
Tez (Doktora) -- İstanbul Teknik Üniversitesi, Enerji Enstitüsü, 2006Thesis (Ph.D.) -- İstanbul Tech...
Using certain well-known properties of chebyshev polynomials, a simple and highly efficient approach...
The study of the steady-state solutions of neutron transport equation requires the introduction of a...
The alpha- and k-effective eigenproblems describe the criticality and fundamental neutron flux mode ...
An accelerated numerical method is developed for one-speed one-dimensional neutron transport eigenva...