Abstract: "Safety analysis of nuclear reactors strongly relies on numerical simulation of the reactor core. A central problem is the determination of the neutron distribution. This is usually done by treating neutron motion as a diffusion process and solving the stationary multigroup neutron di...

Ausführliche Beschreibung

Bibliographische Detailangaben

1. Verfasser:	Schmid, Werner (VerfasserIn)
Format:	Buch
Sprache:	German
Veröffentlicht:	München 1994
Schriftenreihe:	Technische Universität <München>: TUM-MATH 9407
Schlagworte:	Mathematisches Modell Differential equations, Partial > Numerical solutions Eigenvalues Multigrid methods (Numerical analysis) Neutron transport theory > Mathematical models
Zusammenfassung:	Abstract: "Safety analysis of nuclear reactors strongly relies on numerical simulation of the reactor core. A central problem is the determination of the neutron distribution. This is usually done by treating neutron motion as a diffusion process and solving the stationary multigroup neutron diffusion equations. From a mathematical point of view these equations define an eigenvalue problem for a system of partial differential equations that leads to a generalized eigenproblem after discretization. Multigrid methods can be applied efficiently to this problem. To use here the full potential of multigrid methods they must be used very carefully because of the singularity of the problem. One approach is to apply multigrid as iterative solver within inverse iteration for the eigenproblem. Alternatively, multigrid may be applied directly to the eigenproblem when the multigrid cycles are adjusted carefully to the special type of equation. We consider both possibilities using ideas of Bank, Brandt, Hackbusch, and McCormick and compare the performance of the various methods for 2-D problems. It appears that a so-called direct approach may be an interesting alternative to inverse iteration."
Beschreibung:	22 S. graph. Darst.