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Main Authors: Prusachenko, P. S., Grozdanov, D. N., Fedorov, N. A., Kopatch, Yu. N., Pampushik, G. V., Kharlamov, P. I., Skoy, V. R., Ruskov, I. N., Tretyakova, T. Yu., Andreev, A. V., Hramco, C., Filonchik, P. G., collaboration, TANGRA
Format: Preprint
Published: 2025
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Online Access:https://arxiv.org/abs/2508.19925
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author Prusachenko, P. S.
Grozdanov, D. N.
Fedorov, N. A.
Kopatch, Yu. N.
Pampushik, G. V.
Kharlamov, P. I.
Skoy, V. R.
Ruskov, I. N.
Tretyakova, T. Yu.
Andreev, A. V.
Hramco, C.
Filonchik, P. G.
collaboration, TANGRA
author_facet Prusachenko, P. S.
Grozdanov, D. N.
Fedorov, N. A.
Kopatch, Yu. N.
Pampushik, G. V.
Kharlamov, P. I.
Skoy, V. R.
Ruskov, I. N.
Tretyakova, T. Yu.
Andreev, A. V.
Hramco, C.
Filonchik, P. G.
collaboration, TANGRA
contents In this work, differential cross sections of $γ$-ray emission produced in nuclear reactions induced by $14.1$~MeV neutrons are measured for the $4.439$~MeV line from carbon, as well as for $10$ individual $γ$-ray lines from aluminum, $6$ from silicon, $8$ from calcium, $16$ from titanium, $6$ from chromium, and $14$ from iron. The measurements were conducted using the tagged neutron method with four LaBr$_3$(Ce) scintillation detectors positioned at angles of $25^{\circ}$, $45^{\circ}$, $60^{\circ}$, and $70^{\circ}$ relative to the generator target -- sample center axis. A neutron generator capable of producing $16$ separate beams of tagged neutrons was employed, which, combined with the detector system, enabled the determination of differential cross-sections for $64$ distinct angle values in the range of $17^{\circ}$ to $89^{\circ}$. To simplify data visualization, the angular distributions were divided into $5^{\circ}$ intervals, with weighted mean values of the angle and differential cross-section calculated for each interval. Corrections for multiple neutron scattering and attenuation, $γ$-ray attenuation, and total detection efficiency, computed using GEANT4, were accounted for in the cross-section calculations. Additional measurements were performed to validate the correction calculations. The total $γ$-ray emission cross-sections were obtained by approximating the angular distributions with even-order Legendre polynomial expansions up to the $6$th degree, followed by integration over the full solid angle. The total systematic error for the obtained data was estimated as $9$\,\%.
format Preprint
id arxiv_https___arxiv_org_abs_2508_19925
institution arXiv
publishDate 2025
record_format arxiv
spellingShingle Measurement of the differential and total cross-sections of $γ$-ray emission induced by $14.1$ MeV neutrons for C, Al, Si, Ca, Ti, Cr, and Fe using the tagged neutron method
Prusachenko, P. S.
Grozdanov, D. N.
Fedorov, N. A.
Kopatch, Yu. N.
Pampushik, G. V.
Kharlamov, P. I.
Skoy, V. R.
Ruskov, I. N.
Tretyakova, T. Yu.
Andreev, A. V.
Hramco, C.
Filonchik, P. G.
collaboration, TANGRA
Nuclear Experiment
Nuclear Theory
In this work, differential cross sections of $γ$-ray emission produced in nuclear reactions induced by $14.1$~MeV neutrons are measured for the $4.439$~MeV line from carbon, as well as for $10$ individual $γ$-ray lines from aluminum, $6$ from silicon, $8$ from calcium, $16$ from titanium, $6$ from chromium, and $14$ from iron. The measurements were conducted using the tagged neutron method with four LaBr$_3$(Ce) scintillation detectors positioned at angles of $25^{\circ}$, $45^{\circ}$, $60^{\circ}$, and $70^{\circ}$ relative to the generator target -- sample center axis. A neutron generator capable of producing $16$ separate beams of tagged neutrons was employed, which, combined with the detector system, enabled the determination of differential cross-sections for $64$ distinct angle values in the range of $17^{\circ}$ to $89^{\circ}$. To simplify data visualization, the angular distributions were divided into $5^{\circ}$ intervals, with weighted mean values of the angle and differential cross-section calculated for each interval. Corrections for multiple neutron scattering and attenuation, $γ$-ray attenuation, and total detection efficiency, computed using GEANT4, were accounted for in the cross-section calculations. Additional measurements were performed to validate the correction calculations. The total $γ$-ray emission cross-sections were obtained by approximating the angular distributions with even-order Legendre polynomial expansions up to the $6$th degree, followed by integration over the full solid angle. The total systematic error for the obtained data was estimated as $9$\,\%.
title Measurement of the differential and total cross-sections of $γ$-ray emission induced by $14.1$ MeV neutrons for C, Al, Si, Ca, Ti, Cr, and Fe using the tagged neutron method
topic Nuclear Experiment
Nuclear Theory
url https://arxiv.org/abs/2508.19925