International audienceThis work investigates the solution of the multigroup neutron transport equation with a discrete ordinatesmethod. More specifically, it focuses on the k-eigenvalue problem of the equation. In this case, the variablesof interest are the largest eigenvalue (keff) and the corresponding eigenmode is called the fundamentalmode. Mathematically, this problem is usually solved using the power iteration method. However, theconvergence of this algorithm can be very slow, especially if the dominance ratio is high as is the case insome reactor physics applications. Thus, the power iteration method has to be accelerated in some ways toimprove its convergence.One such acceleration is the Chebyshev acceleration method [2] which has b...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
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...
This work focuses on the k-eigenvalue problem of the neutron transport equation. The variables of in...
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 factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
The Anderson Acceleration (AA) scheme is applied and investigated in neutronics and thermal-hydrauli...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
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...
This work focuses on the k-eigenvalue problem of the neutron transport equation. The variables of in...
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 factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The solution of the eigenvalue problem for neutron transport is of utmost importance in the field o...
The Anderson Acceleration (AA) scheme is applied and investigated in neutronics and thermal-hydrauli...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
Graduate School. In this work we propose using Newton’s method, specifically the inexact Newton-GMRE...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
We have developed a Monte Carlo method that calculates multiple perturbation effects in the eigenval...
An accelerated numerical method is developed for one-speed one-dimensional neutron transport eigenva...