4.5 Article

New cross-section measurements for the (n, 2n), (n, p), and (n, a) reactions on bromine in the 14 MeV region with detailed uncertainty quantification

Journal

CHINESE PHYSICS C
Volume 47, Issue 3, Pages -

Publisher

IOP Publishing Ltd
DOI: 10.1088/1674-1137/aca9bf

Keywords

Br-79.81 isotopes; 14 MeV neutrons; (n, 2n), (n, p), and (n, a) reactions; cross-sections; covariance analysis

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The cross-sections of several neutron reactions on bromine isotopes were measured at specific neutron energies using offline gamma-ray spectrometry and neutron activation. Monoenergetic neutrons were generated via a nuclear reaction and the reaction products were detected using a high-purity germanium detector. The obtained data can improve the accuracy of related databases and verify nuclear reaction models.
Measurement of the cross-sections of the Br-79(n, 2n)Br-78, Br-81(n, p)Se-81m, Br-81(n, alpha)As-78, and Br-79(n, alpha)As-76 reactions was performed at specific neutron energies, precisely, 13.5 & PLUSMN;0.2, 14.1 & PLUSMN;0.2, 14.4 & PLUSMN;0.2, and 14.8 & PLUSMN;0.2 MeV, relative to the standard Nb-93(n, 2n)Nb-92m and Al-27(n, alpha)Na-24 reference reactions using offline gamma-ray spectrometry and neutron activation. Monoenergetic neutrons were generated at the China Academy of Engineering Physics via a H-3(d, n)He-4 reaction using the K-400 Neutron Generator equipped with a solid H-3-Ti based target. The activity of the reaction produce was obtained using a high-purity germanium detector. The cross-sections of the (n, 2n), (n, p), and (n, alpha) reactions on the bromine isotopes were measured in the 13-15 MeV neutron energy range. The covariance analysis approach was employed for a thorough inspection of any uncertainties within the measured cross-section data. A discussion and comparison of the observed outcome were carried out with previously published data, especially with the results of the JENDL-4.0, JEFF-3.3, TENDL-2019, and ENDF/B-VIII.0 data libraries, along with the theoretical excitation function curve derived by employing the TALYS-1.95 program. Improved cross-section restrictions for the investigated processes in the 13-15 MeV neutron energy range will be obtained using the current findings, which will help to raise the caliber of associated databases. Furthermore, the parameters of relevant nuclear reaction models can be verified using this data.

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