Published 2013 | Version v1
Book

Homogenization method based on the inverse problem

  • 1. Centre for Energy Research, Hungarian Academy of Sciences, 114 POB 49, H-1525 Budapest (Hungary)

Description

We present a method for deriving homogeneous multi-group cross sections to replace a heterogeneous region's multi-group cross sections; providing that the fluxes and the currents on the external boundary, and the region averaged fluxes are preserved. The method is developed using diffusion approximation to the neutron transport equation in a symmetrical slab geometry. Assuming that the boundary fluxes are given, two response matrices (RMs) can be defined. The first derives the boundary current from the boundary flux, the second derives the flux integral over the region from the boundary flux. Assuming that these RMs are known, we present a formula which reconstructs the multi-group cross-section matrix and the diffusion coefficients from the RMs of a homogeneous slab. Applying this formula to the RMs of a slab with multiple homogeneous regions yields a homogenization method; which produce such homogenized multi-group cross sections and homogenized diffusion coefficients, that the fluxes and the currents on the external boundary, and the region averaged fluxes are preserved. The method is based on the determination of the eigenvalues and the eigenvectors of the RMs. We reproduce the four-group cross section matrix and the diffusion constants from the RMs in numerical examples. We give conditions for replacing a heterogeneous region by a homogeneous one so that the boundary current and the region-averaged flux are preserved for a given boundary flux. (authors)

Part of:
Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
978-0-89448-700-2
Imprint Title
Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013
Imprint Pagination
3016 p.
Journal Page Range
p. 842-853

Conference

Title
2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering
Acronym
M and C 2013
Dates
5-9 May 2013
Place
Sun Valley, ID (United States)

INIS

Country of Publication
United States
Country of Input or Organization
France
INIS RN
45033718
Subject category
S97: MATHEMATICAL METHODS AND COMPUTING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
APPROXIMATIONS; CROSS SECTIONS; CURRENTS; DIFFUSION EQUATIONS; EIGENFUNCTIONS; EIGENVALUES; EIGENVECTORS; GEOMETRY; HOMOGENIZATION METHODS; INTEGRALS; NEUTRON TRANSPORT THEORY
Descriptors DEC
CALCULATION METHODS; DIFFERENTIAL EQUATIONS; EQUATIONS; FUNCTIONS; MATHEMATICS; PARTIAL DIFFERENTIAL EQUATIONS; TRANSPORT THEORY

Optional Information

Notes
7 refs.