The main goal of this work is to examine efficient methods for solving neutron transport and diffusion problems on parallel architecture computers. Using geometric domain decomposition methods, we describe a modified (parallel) version of the standard (scalar) Source Iteration (SI) scheme to solve the diamond-differenced discrete ordinates (S$\sb{\rm N}$) equations for one-group, isotropic scattering and isotropic source transport problems. This parallel SI method consists of subdividing the spatial subdomain for the problem and performing the transport sweeps independently on each subdomain (processor). Results of test runs for one-dimensional transport problems on the Ncube/six, a distributed memory message passing computer, and for x,y-g...
Scalable parallel algorithm for particle transport is one of the main application fields in high-per...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
The diffusion synthetic acceleration (DSA) method is a powerful, stable, efficient iteration method ...
Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes...
Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes...
The multigrid method has been shown to be the most effective general method for solving the multi-di...
. The focus of this paper is on a parallel algorithm for solving the transport equations in a slab ...
Effective preconditioning of neutron diffusion problems is necessary for the development of efficien...
One of the iterative methods which is used to solve the discretized transport equation is called the...
his paper examines two established preconditioners which were developed to accelerate the solution o...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
Les schémas de calcul déterministes permettent une modélisation à moindre coût du comportement de la...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
Abstract: The construction of the P1SA scheme for acceleration of inner and outer iteratio...
Scalable parallel algorithm for particle transport is one of the main application fields in high-per...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...
The diffusion synthetic acceleration (DSA) method is a powerful, stable, efficient iteration method ...
Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes...
Neutron transport codes are essential tools in nuclear reactor and shielding design. Transport codes...
The multigrid method has been shown to be the most effective general method for solving the multi-di...
. The focus of this paper is on a parallel algorithm for solving the transport equations in a slab ...
Effective preconditioning of neutron diffusion problems is necessary for the development of efficien...
One of the iterative methods which is used to solve the discretized transport equation is called the...
his paper examines two established preconditioners which were developed to accelerate the solution o...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
Les schémas de calcul déterministes permettent une modélisation à moindre coût du comportement de la...
Computer codes involving neutron transport theory for nuclear engineering applications always requir...
Abstract: The construction of the P1SA scheme for acceleration of inner and outer iteratio...
Scalable parallel algorithm for particle transport is one of the main application fields in high-per...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The linear Boltzmann transport equation (BTE) is an integro-differential equation arising in determi...