Published 2011
| Version v1
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On the analytical solution of the one-dimensional two energy group neutron diffusion equation with source in cylinder geometry by the Hankel Transform
- 1. Universidade Federal do Rio Grande do Sul (PPGMAp/UFRGS), Porto Alegre, RS (Brazil)
Description
In this work we solve the one-dimensional diffusion equation for neutrons of General Perturbation Theory, in a two energy group model and in homogeneous cylinder geometry by the Hankel Transform. The analytical solution of the transformed problem in matrix form is diagonalized and the scalar neutron flux for two energy groups is obtained by inversion of the Hankel transform. We show as results the fast and thermal flux and compare them with findings from the literature. (author)
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- INIS-BR--17051
Conference
- Title
- International conference on mathematics and computational methods applied to nuclear science and engineering
- Acronym
- M&C 2011
- Dates
- 8-12 May 2011
- Place
- Rio de Janeiro, RJ (Brazil)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 48022293
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANALYTICAL SOLUTION; CYLINDERS; GEOMETRY; HANKEL TRANSFORM; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON TRANSPORT; PERTURBATION THEORY; REACTORS; SCALARS
- Descriptors DEC
- DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; INTEGRAL TRANSFORMATIONS; MATHEMATICAL SOLUTIONS; MATHEMATICS; NEUTRAL-PARTICLE TRANSPORT; PARTIAL DIFFERENTIAL EQUATIONS; RADIATION FLUX; RADIATION TRANSPORT; TRANSFORMATIONS