Convergence acceleration methods for even-parity transport were developed that have the potential to speed up transport calculations and provide a natural avenue for an implicitly coupled multiphysics code. An investigation was performed into the acceleration properties of the introduction of a nonlinear quasi-diffusion-like tensor in linear and nonlinear solution schemes. Using the tensor reduced matrix as a preconditioner for the conjugate gradients method proves highly efficient and effective. The results for the linear and nonlinear case serve as the basis for further research into the application in a full three-dimensional spherical-harmonics even-parity transport code. Once moved into the nonlinear solution scheme, the implicit coupl...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Abstract – This paper proposes a new acceleration method for neutron transport calculations: the gen...
Convergence acceleration methods for even-parity transport are being developed that have the potenti...
The present work concerns some aspects of the optimization of the synthesis acceleration techniques ...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
The factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
The convergence of the approximate method, referred to as An, to study the solution of the monokinet...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
In this thesis, we discuss a coupling algorithm to model simplified fast burst reactor dynamics. Kad...
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or pho...
The interactions between neutron radiation and matter are nonlinear. Specifically, certain neutron ...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Abstract – This paper proposes a new acceleration method for neutron transport calculations: the gen...
Convergence acceleration methods for even-parity transport are being developed that have the potenti...
The present work concerns some aspects of the optimization of the synthesis acceleration techniques ...
Abstract: The rate of convergence of the iterative algorithm for solving the transport equ...
The factors introducing error in the solution of the Boltzmann transport equation, such as spatial d...
The convergence of the approximate method, referred to as An, to study the solution of the monokinet...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
The deterministic solution of the neutron transport problem entails the coupled solution of several ...
In this thesis, we discuss a coupling algorithm to model simplified fast burst reactor dynamics. Kad...
The simulation of singular nonlinear transport equation is obtained via corresponding neutron or pho...
The interactions between neutron radiation and matter are nonlinear. Specifically, certain neutron ...
Nuclear reactor design requires the calculation of integral core parameters and power and radiation ...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
Abstract – This paper proposes a new acceleration method for neutron transport calculations: the gen...