Investigation of 58Ni(n,p)58Co reaction cross-section with covariance analysis

Investigation of 58Ni(n,p)58Co reaction cross-section with covariance analysis

WoS Article

The excitation function of the Ni-58(n,p)Co-58 reaction was measured using the well-established neutron activation technique and gamma-ray spectroscopy. Neutrons in the energy range of 1.7 to 2.7 MeV were generated using the Li-7(p,n) reaction. The neutron flux was measured using the standard In-115(n,n ')(115)mIn monitor reaction. The results of the neutron spectrum averaged cross-section of Ni-58(n,p)Co-58 reactions were compared with existing cross-section data available in the EXFOR data library as well as with various evaluated data libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, and CENDL-3.2. Theoretical calculations were performed using the nuclear reaction code TALYS. Various nuclear level density (NLD) models were tested, and their results were compared with the present findings. Realistic NLDs were also obtained through the spectral distribution method (SDM). The cross-section results, along with the absolute errors, were obtained by investigating the uncertainty propagation and using the covariance technique. Corrections for gamma-ray true coincidence summing, low-energy background neutrons, and gamma-ray self attenuation were performed. The experimental cross-section obtained in the present study is consistent with previously published experimental data, evaluated libraries, and theoretical calculations carried out using the TALYS code.

The excitation function of the Ni-58(n,p)Co-58 reaction was measured using the well-established neutron activation technique and gamma-ray spectroscopy. Neutrons in the energy range of 1.7 to 2.7 MeV were generated using the Li-7(p,n) reaction. The neutron flux was measured using the standard In-115(n,n ')(115)mIn monitor reaction. The results of the neutron spectrum averaged cross-section of Ni-58(n,p)Co-58 reactions were compared with existing cross-section data available in the EXFOR data library as well as with various evaluated data libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, and CENDL-3.2. Theoretical calculations were performed using the nuclear reaction code TALYS. Various nuclear level density (NLD) models were tested, and their results were compared with the present findings. Realistic NLDs were also obtained through the spectral distribution method (SDM). The cross-section results, along with the absolute errors, were obtained by investigating the uncertainty propagation and using the covariance technique. Corrections for gamma-ray true coincidence summing, low-energy background neutrons, and gamma-ray self attenuation were performed. The experimental cross-section obtained in the present study is consistent with previously published experimental data, evaluated libraries, and theoretical calculations carried out using the TALYS code.

nuclear reactions; (n,p) reaction; cross-section measurement; covariance analysis; nuclear level density

nuclear reactions; (n,p) reaction; cross-section measurement; covariance analysis; nuclear level density

HINGU, A.; MUKHERJEE, S.; PARASHARI, S.; SANGEETA, A.; GANDHI, A.; UPADHYAY, M.; CHOUDHARY, M.; BAMAL, S.; SINGH, N.; MISHRA, G.; DE, S.; SOOD, S.; PRASAD, S.; SAXENA, G.; KUMAR, A.; R.G., T.; AGRAWAL, B.; KATOVSKÝ, K.; KUMAR, A.

2024

22.11.2023

IOP Publishing Ltd

China

2058-6132

Chinese Physics C

48

2

People's Republic of China

024001

024014

13

https://iopscience.iop.org/journal/1674-1137

http://hdl.handle.net/