Add to ORKGThe multigrid method has been shown to be the most effective general method for solving the multi-dimensional diffusion equation encountered in neutronics. This being the method of choice, we develop a strategy for implementing the multigrid method on computers of massively parallel architecture. This leads us to strategies for parallelizing the relaxation, contraction (interpolation), and prolongation operators involved in the method. We then compare the efficiency of our parallel multigrid with other parallel methods for solving the diffusion equation on selected problems encountered in reactor physics
Abstract. We consider optimal-scaling multigrid solvers for the linear systems that arise from the d...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
The multigrid algorithm is a fast and efficient (in fact provably optimal) method for solving a wide...
. The focus of this paper is on a parallel algorithm for solving the transport equations in a slab ...
The Finite Difference Method (FDM) is a common approach for solving the multigroup neutron diffusion...
The complexity of the future processing models and the need for three-dimensional simulation require...
Abstract: Parallel multigrid method for elliptic difference equations. Anisotropic diffusi...
Effective preconditioning of neutron diffusion problems is necessary for the development of efficien...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Abstract: Multigrid method is widely used for computations of diffusion, fluid dynamics, e...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
Abstract. We consider optimal-scaling multigrid solvers for the linear systems that arise from the d...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
The main goal of this work is to examine efficient methods for solving neutron transport and diffusi...
The multigrid algorithm is a fast and efficient (in fact provably optimal) method for solving a wide...
. The focus of this paper is on a parallel algorithm for solving the transport equations in a slab ...
The Finite Difference Method (FDM) is a common approach for solving the multigroup neutron diffusion...
The complexity of the future processing models and the need for three-dimensional simulation require...
Abstract: Parallel multigrid method for elliptic difference equations. Anisotropic diffusi...
Effective preconditioning of neutron diffusion problems is necessary for the development of efficien...
Three complementary methods have been implemented in the code Denovo that accelerate neutral particl...
The VARIANT code solves the multigroup steady-state neutron diffusion and transport equation in thre...
Abstract: Multigrid method is widely used for computations of diffusion, fluid dynamics, e...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
Abstract. We consider optimal-scaling multigrid solvers for the linear systems that arise from the d...
The focus of the research was on developing parallel computing algorithm for solving eigen-values of...
This paper developes a new parallelized interative algorithm for solving the neutron diffusion equat...