Published January 1994 | Version v1
Report Open

The numerical analysis of eigenvalue problem solutions in the multigroup diffusion theory

Creators

  • 1. Institute of Atomic Energy, Otwock-Swierk (Poland)

Description

In this paper a general iteration strategy for solving the discrete form of multidimensional neutron diffusion equations is described. Usually the solution method is based on the system of inner and outer iterations. The presented matrix formalism allows us to visualize clearly, how the used matrix splitting influences the structure of the matrix in an eigenvalue problem to be solved as well as the independence between inner and outer iterations within global iterations. To keep the page limit, the present version of the paper consists only with first three of five sections given in the original paper under the same title (which will be published soon). (author). 13 refs

Files

25046125.pdf

Files (261.0 kB)

Name Size Download all
md5:a630732ec1edb7ef3c880a5dc2a5943a
261.0 kB Preview Download
Part of:
Reactor physics and reactor computations

Additional details

Publishing Information

Imprint Title
Reactor Physics and reactor computations
Imprint Pagination
814 p.
Journal Page Range
p. 641-653.
Report number
INIS-mf--13907

Conference

Title
International conference on reactor physics and reactor computations.
Dates
23-26 Jan 1994.
Place
Tel Aviv (Israel).

INIS

Country of Publication
Israel
Country of Input or Organization
Israel
INIS RN
25046125
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ITERATIVE METHODS; MANY-DIMENSIONAL CALCULATIONS; NEUTRON DIFFUSION EQUATION; NUMERICAL SOLUTION; RESPONSE MATRIX METHOD
Descriptors DEC
CALCULATION METHODS; EQUATIONS; REACTOR KINETICS EQUATIONS

Optional Information