The measurement of neutron activation cross sections in the energy range 3.5 Mev to 6.0 Mev

Abdul Jalil, Nabil (1980). The measurement of neutron activation cross sections in the energy range 3.5 Mev to 6.0 Mev. PHD thesis, Aston University.

Abstract

A measurement of the 46•47•48Ti(n,n)46•47•48sc reaction cross-sections has been performed relative to the U-235 fission cross-sections over the neutron energy range of 3.5 Mev to 6.0 Mev. e q' J ir 2 d for f J. I J < '!a 1 >.sis The uranium-235 content,< was aetermined from both 27/ and low geometry alpha-particle assay. Fissions from the U-235 standard were detected in a low mass parallel-plate ionisation chamber. To provide a satisfactory neutron flux, a deuterium gas taget was designed to withstand up to three times the maximum beam power densities Permissible in conventional gas targets. The gamma-ray activities induced in the irradiated samples were determined using a 7.62 em x 7.62 em Nai(TI) detector. The gamma-ray detection efficiencies were corrected for sample self­ scattering and self-absorption using the Monte Carlo method. A second Monte Carlo program was developed to correct for irradiation geometry. Corrections were applied for neutron scattering within the sample and fission chamber, and the thermal and back­ ground neutrons. The present measurements are in agreement with other measurements, whilst nroviding greater accuracies.

Divisions: Engineering & Applied Sciences
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Institution: Aston University
Uncontrolled Keywords: measurement,neutron activation,cross sections,energy range 3.5 Mev - 6.0 Mev
Completed Date: 1980
Authors: Abdul Jalil, Nabil

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