Analytical solution of the multigroup neutron diffusion kinetic equation in one-dimensional cartesian geometry by the integral transform technique
Description
The objective of this work is to obtain an analytical solution of the neutron diffusion kinetic equation in one-dimensional cartesian geometry, to monoenergetic and multigroup problems. These equations are of the type stiff, due to large differences in the orders of magnitude of the time scales of the physical phenomena involved, which make them difficult to solve. The basic idea of the proposed method is applying the spectral expansion in the scalar flux and in the precursor concentration, taking moments and solving the resulting matrix problem by the Laplace transform technique. Bearing in mind that the equation for the precursor concentration is a first order linear differential equation in the time variable, to enable the application of the spectral method we introduce a fictitious diffusion term multiplied by a positive value which tends to zero. This procedure opened the possibility to find an analytical solution to the problem studied. We report numerical simulations and analysis of the results obtained with the precision controlled by the truncation order of the series. (author)
Files
41052997.pdf
Files
(1.6 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:7451ad2ed453e541c872fa1b9582ef4a
|
1.6 MB | Preview Download |
Additional details
Additional titles
- Original title (Portuguese)
- Solucao analitica da equacao cinetica de difusao multigrupo de neutrons em geometria cartesiana unidimensional pela tecnica da transformada integral
Publishing Information
- Imprint Pagination
- 58 p.
- Report number
- INIS-BR--6731
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 41052997
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ANALYTICAL SOLUTION; DIFFERENTIAL EQUATIONS; HOMOGENIZATION METHODS; LAPLACE TRANSFORMATION; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; REACTOR KINETICS; REACTOR KINETICS EQUATIONS; REACTORS
- Descriptors DEC
- CALCULATION METHODS; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; EQUATIONS; INTEGRAL TRANSFORMATIONS; KINETICS; MATHEMATICAL SOLUTIONS; PARTIAL DIFFERENTIAL EQUATIONS; TRANSFORMATIONS; TRANSPORT THEORY