Approximation for the adjoint neutron spectrum
- 1. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear
Description
The proposal of this work is the determination of an analytical approximation which is capable to reproduce the adjoint neutron flux for the energy range of the narrow resonances (NR). In a previous work we developed a method for the calculation of the adjoint spectrum which was calculated from the adjoint neutron balance equations, that were obtained by the collision probabilities method, this method involved a considerable quantity of numerical calculation. In the analytical method some approximations were done, like the multiplication of the escape probability in the fuel by the adjoint flux in the moderator, and after these approximations, taking into account the case of the narrow resonances, were substituted in the adjoint neutron balance equation for the fuel, resulting in an analytical approximation for the adjoint flux. The results obtained in this work were compared to the results generated with the reference method, which demonstrated a good and precise results for the adjoint neutron flux for the narrow resonances. (author)
Additional details
Additional titles
- Original title (Portuguese)
- Aproximacao para o espectro adjunto 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
- [5 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
- 33043581
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADJOINT FLUX; CALCULATION METHODS; CROSS SECTIONS; DOPPLER BROADENING; FUEL ELEMENTS; NEUTRON SPECTRA; RESONANCE NEUTRONS; URANIUM 238
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYONS; ELEMENTARY PARTICLES; EVEN-EVEN NUCLEI; FERMIONS; HADRONS; HEAVY NUCLEI; ISOTOPES; LINE BROADENING; NEUTRON FLUX; NEUTRONS; NUCLEI; NUCLEONS; RADIATION FLUX; RADIOISOTOPES; REACTOR COMPONENTS; SPECTRA; SPONTANEOUS FISSION RADIOISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 5 refs.,3 graphs Imprint:Published only in CD-Rom