Published 2009 | Version v1
Miscellaneous Open

An analytical solution of the one-dimensional neutron diffusion kinetic equation in cartesian geometry

  • 1. Universidade Federal do Rio Grande do Sul (UFRGS), Porto Alegre, RS (Brazil). Programa de Pos-Graduacao em Engenharia Mecanica
  • 2. Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

Description

In this work we report an analytical solution for the monoenergetic neutron diffusion kinetic equation in cartesian geometry. Bearing in mind that the equation for the delayed neutron precursor concentration is a first order linear differential equation in the time variable, to make possible the application of the GITT approach to the kinetic equation, we introduce a fictitious diffusion term multiplied by a positive small value ε. By this procedure, we are able to solve this set of equations. Indeed, applying the GITT technique to the modified diffusion kinetic equation, we come out with a matrix differential equation which has a well known analytical solution when ε goes to zero. We report numerical simulations as well study of numerical convergence of the results attained. (author)

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Additional details

Publishing Information

Imprint Pagination
[7 p.]
Report number
INIS-BR--7445

Conference

Title
International nuclear atlantic conference. Innovations in nuclear technology for a sustainable future; 16. Brazilian national meeting on reactor physics and thermal hydraulics; 9. Brazilian national meeting on nuclear applications; 1. Meeting on nuclear industry
Acronym
INAC 2009
Dates
27 Sep - 2 Oct 2009
Place
Rio de Janeiro, RJ (Brazil)

Optional Information

Notes
Published only in CD-Rom. Code: r16_91_fullpaper.pdf