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.
|Date of Award||1980|
- neutron activation
- cross sections
- energy range 3.5 Mev - 6.0 Mev