New solution methods suitable for efficient parallel computation of reactor spatial kinetics problems are presented. A transient fixed source problem is formulated at each time point by applying the theta time differencing method and a second-order precursor integration technique to the time-dependent neutron balance equation. The spatial solution of the fixed source problem is obtained by employing the nonlinear nodal method. The coarse mesh finite difference problems appearing in the nonlinear iteration are solved by a preconditioned Krylov subspace method. A preconditioner suitable for three-dimensional coarse mesh neutron diffusion problems is developed based on the blockwise incomplete LU factorization. Parallel computation of the nonl...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The time-dependent neutron diffusion equation approximates the neutronic power evolution inside a nu...
: 2 Text: 26 Figures: 3 Tables: 3 Abstract - Methods are proposed for the efficient parallel sol...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
New neutronics solution methods implemented in the EPRI spatial kinetics code ARROTTA are presented....
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
This paper describes an efficient and nonlinearly consistent parallel so-lution methodology for solv...
In this paper, the capabilities of reduced order methods, with application to nuclear reactor core s...
In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient mo...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The time-dependent neutron diffusion equation approximates the neutronic power evolution inside a nu...
: 2 Text: 26 Figures: 3 Tables: 3 Abstract - Methods are proposed for the efficient parallel sol...
A new nodal method for the solution of multigroup multidimensional diffusion problems in hexagonal g...
New neutronics solution methods implemented in the EPRI spatial kinetics code ARROTTA are presented....
548 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1988.A family of highly efficient ...
The accurate knowledge of the time-dependent spatial flux distribution in nuclear reactor is require...
313 p.Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 1985.A new high-accuracy, coarse-m...
The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform...
The numerical solution of time dependent neutron diffusion approximation to the transport equation i...
A nodal method is developed for the solution of the neutron-diffusion equation in two- and three-dim...
This paper describes an efficient and nonlinearly consistent parallel so-lution methodology for solv...
In this paper, the capabilities of reduced order methods, with application to nuclear reactor core s...
In this paper we present a time-parallel algorithm for the 3D neutrons calculation of a transient mo...
A nodal method of the so-called analytical physical type, using partial currents as variables, is ap...
Abstract: Algorithms are obtained to compute spatial kinetics of nuclear reactor in diffus...
The time-dependent neutron diffusion equation approximates the neutronic power evolution inside a nu...