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Homogenization of a spectral equation in neutron transport. (Homogénéisation d’une équation spectrale du transport neutronique.) (French. Abridged English version) Zbl 0888.45002
Summary: We study the homogenization of an eigenvalue problem for the neutron transport in a periodic heterogeneous domain. We prove that the neutronic flux can be factorized as a product of two terms, up to a remainder which converges strongly to zero with the period. The first term is the first eigenvector of the transport equation in the periodicity cell. The second term is the solution of an eigenvalue problem for a diffusion equation in the homogenized domain. This result justifies and improves the engineering procedure used in practice for nuclear reactor cores computations.
Reviewer: Reviewer (Berlin)

MSC:
45C05 Eigenvalue problems for integral equations
45K05 Integro-partial differential equations
82C70 Transport processes in time-dependent statistical mechanics
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