Sensitivity coefficients for response matrices
Creators
- 1. Comissao Nacional de Energia Nuclear, Rio de Janeiro, RJ (Brazil). Dept. de Reatores
- 2. Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia
Description
Accurate solution of the group diffusion equation for PWR cores requeries explicit treatment of the non-homogeneous macroscopic parameters within each fuel assembly. It is argued that the response matrix approach is a convenient method to handle this problem provided all matrix elements for the non-homogeneous assemblies can be computed. This so called local problem is solved in this paper by a perturbation algorithm which leads to sensitivity coefficients for the power series expansions of the response matrix elements. A numerical study for two representative assemblies of the Indian Point No 2 (IP2) reactor is carried out and response matrices obtained by the perturbative method are compared with values computed by a finite difference program. (author)
Availability note (English)
Available from the Library of Comissao Nacional de Energia Nuclear, RJ, Brazil.Abstract (Portuguese)
Uma solucao precisa para as equacoes de difusao multigrupo para nucleos PWR requer um tratamento explicito dos parametros macroscopicos nao homogeneos, no interior de cada elemento combustivel. E demonstrado que a aproximacao por matrizes resposta e um metodo adequado para tratar este problema, visto que todos os elementos das matrizes para elementos combustiveis heterogeneos podem ser determinados. Este calculo e conhecido com problema local, sendo efetuado por um algoritimo de perturbacao, o qual conduz a coeficientes de sensibilidade para as expansoes em series de potencias dos elementos das matrizes resposta. Um estudo numerico para dois elementos combustiveis representativos do reator Indian Point 2 e, entao, efetuado e as matrizes-resposta obtidas com o metodo perturbativo sao comparadas com os valores calculados por um programa de diferencas finitas. (autor)Additional details
Additional titles
- Original title (Portuguese)
- Coeficientes de sensibilidade para matrizes resposta
Publishing Information
- Imprint Title
- Proceedings of the 7. National Meeting of Reactor Physics and Thermohydraulic. v. 1
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 129-142.
Conference
- Title
- 7. National Meeting of Reactor Physics and Thermohydraulic.
- Dates
- 26-28 Apr 1989.
- Place
- Recife, PE (Brazil).
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 20064142
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ALGORITHMS; DIFFUSION; FUEL ELEMENTS; INDIAN POINT-2 REACTOR; MATRIX ELEMENTS; PERTURBATION THEORY; POWER SERIES; RESPONSE MATRIX METHOD; SENSITIVITY ANALYSIS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EQUATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR KINETICS EQUATIONS; REACTORS; SERIES EXPANSION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Anais do 7. Encontro Nacional de Fisica de Reatores e Termohidraulica. v. 1.