Published 2002 | Version v1
Computer medium

Adjoint P1 equations solution for neutron slowing down

  • 1. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

Description

In some applications of perturbation theory, it is necessary know the adjoint neutron flux, which is obtained by the solution of adjoint neutron diffusion equation. However, the multigroup constants used for this are weighted in only the direct neutron flux, from the solution of direct P1 equations. In this work, the adjoint P1 equations are derived by the neutron transport equation, the reversion operators rules and analogies between direct and adjoint parameters. The direct and adjoint neutron fluxes resulting from the solution of P1 equations were used to three different weighting processes, to obtain the macrogroup macroscopic cross sections. It was found out noticeable differences among them. (author)

Part of:
Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications

Additional details

Additional titles

Original title (Portuguese)
Solucao das equacoes P1 adjuntas para moderacao de neutrons

Publishing Information

Imprint Title
Proceedings of the INAC 2002: International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
Imprint Pagination
[3080 p.]
Journal Page Range
[6 p.]

Conference

Title
International nuclear atlantic conference; 13. Brazilian national meeting on reactor physics and thermal hydraulics; 6. Brazilian national meeting on nuclear applications
Acronym
INAC 2002
Dates
11-16 Aug 2002
Place
Rio de Janeiro, RJ (Brazil)

Optional Information

Notes
3 refs., 2 tabs., 2 graphs Imprint:Published only in CD-Rom