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)
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)
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 33043555
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADJOINT FLUX; CALCULATION METHODS; GROUP CONSTANTS; MULTIGROUP THEORY; NEUTRON DENSITY; NEUTRON DIFFUSION EQUATION; NEUTRON FLUX; NEUTRON SLOWING-DOWN THEORY; NEUTRON TRANSPORT THEORY; P1-APPROXIMATION; PERTURBATION THEORY; TOTAL CROSS SECTIONS
- Descriptors DEC
- CALCULATION METHODS; CROSS SECTIONS; DIFFERENTIAL EQUATIONS; EQUATIONS; NEUTRON FLUX; NEUTRON TRANSPORT THEORY; RADIATION FLUX; SPHERICAL HARMONICS METHOD; TRANSPORT THEORY
Optional Information
- Notes
- 3 refs., 2 tabs., 2 graphs Imprint:Published only in CD-Rom