Cross section determination for TAD materials in quasi mono-energetic neutron spectrum from p(Li) reaction

¹ Brno University of Technology, Faculty of Electrical Engineering and Communication, Department of Electrical Power Engineering, Brno, Czech Republic
² Joint Institute for Nuclear Research, Dubna, Russian Federation
³ Chair of Nuclear Physics, Faculty of Physics, Yerevan State University, Yerevan, Republic of Armenia
⁴ Department of Nuclear Physics and Elementary Particles, Uzhhorod National University, Uzhhorod, Ukraine

^* e-mail: xkrald00@vutbr.cz

Published online: 30 September 2020

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.