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Nondestructive analysis of the natural uranium mass through the measurement of delayed neutrons using the technique of pulsed neutron source; Analise nao destrutiva da massa de uranio natural atraves da medida de neutrons atrasados com o uso da tecnica de fonte pulsada de neutrons rapidos

Abstract

This work presents results of non destructive mass analysis of natural uranium by the pulsed source technique. Fissioning is produced by irradiating the test sample with pulses of 14 MeV neutrons and the uranium mass is calculated on a relative scale from the measured emission of delayed neutrons. Individual measurements were normalised against the integral counts of a scintillation detector measuring the 14 MeV neutron intensity. Delayed neutrons were measured using a specially constructed slab detector operated in anti synchronism with the fast pulsed source. The 14 MeV neutrons were produced via the T(d,n) {sup 4}He reaction using a 400 kV Van de Graaff accelerated operated at 200 kV in the pulsed source mode. Three types of sample were analysed, namely: discs of metallic uranium, pellets of sintered uranium oxide and plates of uranium aluminium alloy sandwiched between aluminium. These plates simulated those of Material Testing Reactor fuel elements. Results of measurements were reproducible to within an overall error in the range 1.6 to 3.9%; the specific error depending on the shape, size and mass of the sample. (author)
Publication Date:
Jul 01, 1979
Product Type:
Thesis/Dissertation
Report Number:
INIS-BR-5902
Resource Relation:
Other Information: TH: Diss. (M.Sc.); 37 refs., 39 figs., 5 tabs
Subject:
07 ISOTOPES AND RADIATION SOURCES; NATURAL URANIUM; NEUTRON BEAMS; PULSED NEUTRON TECHNIQUES; PULSES; RADIATION DETECTION; RADIATION DOSES; RADIATION SOURCES; RADIATIONS; RADIOACTIVITY; RADIOISOTOPES
OSTI ID:
21219214
Research Organizations:
Universidade de Sao Paulo (USP), Sao Paulo, SP (Brazil). Escola Politecnica
Country of Origin:
Brazil
Language:
Portuguese
Other Identifying Numbers:
TRN: BR09V2912087762
Availability:
Available from INIS in electronic form
Submitting Site:
BRN
Size:
124 pages
Announcement Date:
Nov 05, 2009

Citation Formats

Coelho, Paulo Rogerio Pinto. Nondestructive analysis of the natural uranium mass through the measurement of delayed neutrons using the technique of pulsed neutron source; Analise nao destrutiva da massa de uranio natural atraves da medida de neutrons atrasados com o uso da tecnica de fonte pulsada de neutrons rapidos. Brazil: N. p., 1979. Web.
Coelho, Paulo Rogerio Pinto. Nondestructive analysis of the natural uranium mass through the measurement of delayed neutrons using the technique of pulsed neutron source; Analise nao destrutiva da massa de uranio natural atraves da medida de neutrons atrasados com o uso da tecnica de fonte pulsada de neutrons rapidos. Brazil.
Coelho, Paulo Rogerio Pinto. 1979. "Nondestructive analysis of the natural uranium mass through the measurement of delayed neutrons using the technique of pulsed neutron source; Analise nao destrutiva da massa de uranio natural atraves da medida de neutrons atrasados com o uso da tecnica de fonte pulsada de neutrons rapidos." Brazil.
@misc{etde_21219214,
title = {Nondestructive analysis of the natural uranium mass through the measurement of delayed neutrons using the technique of pulsed neutron source; Analise nao destrutiva da massa de uranio natural atraves da medida de neutrons atrasados com o uso da tecnica de fonte pulsada de neutrons rapidos}
author = {Coelho, Paulo Rogerio Pinto}
abstractNote = {This work presents results of non destructive mass analysis of natural uranium by the pulsed source technique. Fissioning is produced by irradiating the test sample with pulses of 14 MeV neutrons and the uranium mass is calculated on a relative scale from the measured emission of delayed neutrons. Individual measurements were normalised against the integral counts of a scintillation detector measuring the 14 MeV neutron intensity. Delayed neutrons were measured using a specially constructed slab detector operated in anti synchronism with the fast pulsed source. The 14 MeV neutrons were produced via the T(d,n) {sup 4}He reaction using a 400 kV Van de Graaff accelerated operated at 200 kV in the pulsed source mode. Three types of sample were analysed, namely: discs of metallic uranium, pellets of sintered uranium oxide and plates of uranium aluminium alloy sandwiched between aluminium. These plates simulated those of Material Testing Reactor fuel elements. Results of measurements were reproducible to within an overall error in the range 1.6 to 3.9%; the specific error depending on the shape, size and mass of the sample. (author)}
place = {Brazil}
year = {1979}
month = {Jul}
}