Bodmann, B. E. J. and de Vilhena, M. T. and Ferreira, L. S. and Bardaji, J. B. (2010) An analytical solver for the multi-group two-dimensional neutron-diffusion equation by integral transform techniques. Il nuovo cimento C, 33 (1). pp. 63-70. ISSN 1826-9885
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Abstract
In this work, we present an analytical solver for neutron diffusion in a rectangular two-dimensional geometry by a two-step integral transform procedure. To this end, we consider a regionwise homogeneous problem for two energy groups, i.e. fast and thermal neutrons, respectively. Each region has its specific physical properties, specified by cross-sections and diffusion constants. The problem is set up by two coupled bi-dimensional diffusion equations in agreement with general perturbation theory. These are solved by integral transforms Laplace transform and generalized integral transform technique yielding analytical expressions for the scalar neutron fluxes. The solutions for neutron fluxes are presented for fast and thermal neutrons in the four regions.
| Item Type: | Article |
|---|---|
| Uncontrolled Keywords: | Neutron transport: diffusion and moderation ; Diffusion |
| Subjects: | 500 Scienze naturali e Matematica > 530 Fisica |
| Depositing User: | Marina Spanti |
| Date Deposited: | 31 Mar 2020 15:18 |
| Last Modified: | 31 Mar 2020 15:18 |
| URI: | http://eprints.bice.rm.cnr.it/id/eprint/16794 |
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