Published 1990 | Version v1
Miscellaneous

Computer calculations and methods from reactivity and neutron flux distribution measurements of IEA-R1 reactor with the new fuel element 130

  • 1. Instituto de Pesquisas Energeticas e Nucleares (IPEN), Sao Paulo, SP (Brazil). Div. de Fisica de Reatores

Description

The thermal neutron flux and core reactivity were measured when a new fuel element (number 130) was inserted into the IEA-R1 reactor core. The thermal neutron flux distribution was measured by gold activation foil (bare and covered with Cadmium) in the fuel element number 130, and the core reactivity gain due a new fuel element was determined using control rod calibration curve. The experimental results were compared to those obtained by CITATION code calculation. The results presented in this work are a good contribution for a better knowledge of IEA-R1 reactor neutronic behaviour. (author)

Additional details

Additional titles

Original title (Portuguese)
Validacao dos metodos de calculos computacionais a partir das medidas de distribuicao de fluxo de enutrons e reatividade do reator IEA-R1 com o novo elemento combustivel 130

Publishing Information

Imprint Title
Proceedings of the 3. General Congress on Nuclear Energy. v. 1
Imprint Pagination
166 p.
Journal Page Range
p. 122-131.

Conference

Title
3. General Congress on Nuclear Energy.
Dates
22-27 Jul 1991.
Place
Rio de Janeiro, RJ (Brazil).

Optional Information

Notes
Imprint:Anais do 3. Congresso Geral de Energia Nuclear. v. 1.