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Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1

Abstract

The work is aimed at obtaining a physical method for neutron flux distribution determination within the reactor core, in order to analyze the project of power increase in the TRIGA IPR-R1 reactor at the Nuclebras Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), located in Belo Horizonte, Minas Gerais, Brazil. The experimental process utilizes the neutron activation technique in impurities of stainless steel welding rods 700 mm long, set in acrylic supports. These rods provide simultaneous information on the thermal and fast neutron fluxes through capture and threshold reactions. The process of detection and counting of activation products utilizes a high resolution Ge (Li) detector and a mechanical scanning device, designed and manufactured at CDTN for burn-up measurements of irradiated fuel elements. Besides its simplicity, the method presents the advantage of substituting high purity imported materials by one easily obtained that also furnishes simultaneous information on the thermal and fast neutron fluxes. Furthermore, values for the absolute thermal neutron flux a long the whole core height are obtained. The procedure consists of the assessment of the thermal neutron flux in a fixed point by means of a conventional detector, and then establishing the correspondence of this measurement with the response of  More>>
Publication Date:
Jun 01, 1985
Product Type:
Thesis/Dissertation
Report Number:
INIS-BR-3522
Reference Number:
SCA: 220600; PA: AIX-26:053221; EDB-95:090166; ERA-20:018495; NTS-96:003000; SN: 95001414199
Resource Relation:
Other Information: TH: Tese (M.Sc.).; PBD: Jun 1985
Subject:
22 NUCLEAR REACTOR TECHNOLOGY; TRIGA-BRAZIL REACTOR; NEUTRON FLUX; ACTIVATION DETECTORS; LI-DRIFTED DETECTORS; NUCLEBRAS; THRESHOLD DETECTORS; WELDING RODS
OSTI ID:
65450
Research Organizations:
Minas Gerais Univ., Belo Horizonte, MG (Brazil). Curso de Pos-graduacao em Ciencias e Tecnicas Nucleares
Country of Origin:
Brazil
Language:
Portuguese
Other Identifying Numbers:
Other: ON: DE95631477; TRN: BR9533243053221
Availability:
INIS; OSTI as DE95631477
Submitting Site:
INIS
Size:
133 p.
Announcement Date:

Citation Formats

Guimaraes, R R.R. Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1. Brazil: N. p., 1985. Web.
Guimaraes, R R.R. Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1. Brazil.
Guimaraes, R R.R. 1985. "Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1." Brazil.
@misc{etde_65450,
title = {Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1}
author = {Guimaraes, R R.R.}
abstractNote = {The work is aimed at obtaining a physical method for neutron flux distribution determination within the reactor core, in order to analyze the project of power increase in the TRIGA IPR-R1 reactor at the Nuclebras Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), located in Belo Horizonte, Minas Gerais, Brazil. The experimental process utilizes the neutron activation technique in impurities of stainless steel welding rods 700 mm long, set in acrylic supports. These rods provide simultaneous information on the thermal and fast neutron fluxes through capture and threshold reactions. The process of detection and counting of activation products utilizes a high resolution Ge (Li) detector and a mechanical scanning device, designed and manufactured at CDTN for burn-up measurements of irradiated fuel elements. Besides its simplicity, the method presents the advantage of substituting high purity imported materials by one easily obtained that also furnishes simultaneous information on the thermal and fast neutron fluxes. Furthermore, values for the absolute thermal neutron flux a long the whole core height are obtained. The procedure consists of the assessment of the thermal neutron flux in a fixed point by means of a conventional detector, and then establishing the correspondence of this measurement with the response of the stainless steel rods. (author). 30 refs, 39 figs, 9 tabs.}
place = {Brazil}
year = {1985}
month = {Jun}
}