Abstract
Threshold activation detectors (TAD) are of great importance for a determination of neutron energy spectra and flux density. For different sources, it is necessary to choose the right combination of materials that cover the estimated spectra. Several different materials were irradiated in a quasi-monoenergetic neutron field with 29.1 MeV peak neutrons energy in the CANAM facility. Neutrons were produced in p + Li-7 reaction in a thin target and the foils were situated in the proton beam axis and close geometry to the Li target. The integral number of protons was established from accelerator telemetry and lithium target activation measurements after the experiment. During the experiment, one long irradiation was done for following foils: Al, Au, Bi, Co, Cu, Fe, In, Mn, Pb, Ta, V, Y and four short irradiations for foils: Cu, Fe, In, Ta, V, W, Y. The foils were irradiated in a sandwich configuration, sorted by cross-section where the materials with higher cross-section were placed in the back of the sandwich. Neutrons produced in the p + Li-7 reaction have a quasi mono-energetic spectrum which provides a suitable basis for cross-section determination. Experimental results were calculated for (n,xn), (n,p) and (n,α) reactions via the dosimetry foils activation method including a gamma-ray spectroscopy method. Several important spectroscopic corrections have to be applied to increase the accuracy of the obtained results, including neutron background suppression. Experimental data will be submitted to the EXFOR database.
Highlights
Well known cross-sections for different neutron reactions are important for most nuclear applications
One of the applications that need a good knowledge of the cross-sections is measuring of a neutron flux density and neutron spectrum with the Threshold activation detectors (TAD)
The use of TAD is wide for example the describing neutron field around some experimental set-ups, channels, and different devices
Summary
Well known cross-sections for different neutron reactions are important for most nuclear applications. Some reactions are described from low energy to high energies, but most of them do not have enough experimental data. One of the applications that need a good knowledge of the cross-sections is measuring of a neutron flux density and neutron spectrum with the TAD. This off-line method uses a difference in energy of thresholds for various nuclear reactions. For spectrum with energy from several hundred keV up to several MeV are important (n,p), (n,n’), and (n,α). The use of TAD is wide for example the describing neutron field around some experimental set-ups, channels, and different devices. The TAD main advantages are simple usage, small dimensions, low cost, and with a large number of detectors is possible to make very accurate measurement during one irradiation
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