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The cross section of the 51 V n , p 51 Ti reaction was measured at 7.87, 13.05 and 16.98 MeV neutron energies using the activation technique and offline γ -ray spectrometry. Vanadium targets were activated along with Al monitor foil to measure the cross section relative to the standard 27 Al n , α 24 Na reference reaction. The quasi-monoenergetic neutron beams were produced via the 7 Li p , n reaction at the 14UD BARC-TIFR Pelletron Facility, Mumbai, India. Statistical nuclear reaction Talys (ver. 1.9) code was used for the theoretical estimations of the 51 V n , p 51 Ti reaction cross section. Additionally, the effects of different input parameters were considered in present work to reproduction of the experimental data more accurately. The experimental data of the present measurements were discussed and compared with the previous measurements taken from the EXFOR compilation and latest evaluations of the ENDF/B-VIII.0, JENDL/AD-2017 and TENDL-2019 libraries. The covariance method was used to estimate the magnitudes of the uncertainties in the present cross section measurements. Furthermore, the different systematic formulae at 14–15 MeV energies were used to calculate the n , p , n , 2 n and n , α reactions cross section for structural material vanadium. The calculated cross sections from the formulae were discussed and compared with the available experimental data. [ABSTRACT FROM AUTHOR]

The cross-section of the 181Ta(n,2n)180Ta reaction has been measured with respect to the 197Au(n,2n)196Au monitor reaction at the incident neutron energy of 14.78± 0.20 MeV, using neutron activation analysis and off-line γ-ray spectrometric technique. The present measurement has been done at the energy where discrepant measured results are available in the EXFOR data library. The result has been compared with evaluated data libraries JEFF-3.3 and ENDF/BVII. 1. The present result has also been supported by theoretical predictions of nuclear model code TALYS1.8 and TALYS- 1.9. The uncertainty and the correlations among the measured cross-section has been studied using co-variance analysis. [ABSTRACT FROM AUTHOR]

Abstract The neutron capture cross-sections have been measured for the 159Tb(n, γ)160Tb reaction at the spectrum average peak neutron energies of 5.08 ± 0.165, 12.47 ± 0.825, and 16.63 ± 0.95 MeV respectively. The experiment has been carried out using the standard neutron activation technique and off-line γ-ray spectrometry. The present measurement has been done for the energies where very few measured results are available in the data library. The results have been compared with ENDF/B-VII.1 and JENDL-4.0 data libraries. The present results have also been supported by theoretical predictions of nuclear model code TALYS 1.9. Detailed covariance analysis was carried out to find the uncertainty and the correlations among the measured cross-sections. Highlights • Tb being an excellent structural metal has several reactor and nuclear medicines based applications. • Tb isotopes are of keen interest of study since they are widely used in nuclear medicine. • Calculations have been performed within the framework of theoretical code Talys-1.9. [ABSTRACT FROM AUTHOR]

The cross-sections for 86Sr (n, 2n)85Sr reaction are measured at neutron energies 19.44 ± 1.02 MeV and 16.81 ± 0.85 MeV wherein there is scarcity of data. The standard neutron activation analysis technique and offline gamma ray spectroscopy have been employed for measurement and analysis of the data. The results are compared with experimental data available in EXFOR database, JEFF-3.3, JENDL-4.0, TENDL-2017 and ENDF/B-VIII.0 evaluated data. The theoretical prediction was incorporated using nuclear modular codes TALYS 1.8 and EMPIRE 3.2.2. A detailed comparative study of experimental results with the theoretical models and various major evaluations has been presented. [ABSTRACT FROM AUTHOR]

The cross sections of the 186W(n,γ) 187W, 182W(n,p) 182Ta, 154Gd(n,2n) 153Gd, and 160Gd(n,2n) 159Gd reactions were measured at the neutron energies 5.08 ± 0.165, 8.96 ± 0.77, 12.47 ± 0.825, and 16.63 ± 0.95 MeV. Standard neutron activation analysis technique and off-line γ ray spectrometry were used for the measurement and analysis of the data. Measurements were done in the energy range where few or no measured data are available. The results from the present work are compared with the literature data based on the EX FOR compilation. The experimental results are supported by theoretical predictions using nuclear modular codes TALYS 1.8 and EMPIRE 3.2.2. The predictability of different one-dimensional models available in TALYS 1.8 and Levden models in EMPIRE 3.2.2 were tested. A detailed comparison of experimental results with theoretical model calculations is made. [ABSTRACT FROM AUTHOR]

Cross sections for the 64Zn(n,2n)63Zn and 67Zn(n,p)67Cu reactions were measured at neutron energies of 17.10 ± 0.82 and 14.98 ± 0.81 MeV by neutron activation techniques and offline γ-ray spectroscopy method. Production of neutron was done by 7Li (p,n)\documentclass[12pt]{minimal}\usepackage{amsmath}\usepackage{wasysym}\usepackage{amsfonts}\usepackage{amssymb}\usepackage{amsbsy}\usepackage{mathrsfs}\usepackage{upgreek}\setlength{\oddsidemargin}{-69pt}\begin{document}$$(p,n)$$\end{document} reaction. The 27Al (n,α)\documentclass[12pt]{minimal}\usepackage{amsmath}\usepackage{wasysym}\usepackage{amsfonts}\usepackage{amssymb}\usepackage{amsbsy}\usepackage{mathrsfs}\usepackage{upgreek}\setlength{\oddsidemargin}{-69pt}\begin{document}$$(n,\alpha )$$\end{document}24Na reaction was used as a neutron flux monitor. Estimations were performed using TALYS-1.95 and EMPIRE 3.2.2 codes with default values. The measured cross sections were compared with literature data taken from the EXFOR database and the latest evaluated data from the ENDF/B-VIII.0, JEFF-3.3, JENDL-5.0 and TENDL-2021 libraries. [ABSTRACT FROM AUTHOR]

Activation and off-line γ-ray spectrometric methods were used to measure the ground and isomeric state (n , 2 n) reaction cross section for 103Rh at two different neutron energies. The standard 27Al (n , α) 24Na reference reaction was used to normalise neutron flux. The proton beam from the 14UD BARC-TIFR Pelletron facility in Mumbai, India, was utilised to create high-energy quasi-monoenergetic neutrons via the 7Li (p , n) reaction. Statistical model calculations including the level density, pre-equilibrium and optical potential model were performed using the TALYS (ver. 1.95) and EMPIRE (ver. 3.2.3) reaction codes. In addition, because of considerable discrepancies in measured data, the literature (n , p) reaction cross section of 52Cr and 48Ti targets were examined theoretically in the present work. The measured cross sections are discussed and compared with the latest evaluated data of the FENDL-3.2b, CENDL-3.2, TENDL-2019, JENDL-5.0, and ENDF/B-VIII.0 libraries, and experimental data based on the EXFOR compilation. The theoretical investigation of the (n , 2 n) reaction cross section was performed for the ground and isomeric state for the first time from reaction threshold to 25 MeV energies. The experimental data corresponding to the ground, isomeric state and isomeric ratio were reproduced consistently by the theoretical calculations. The present experimental results are good with certain literature data and theoretical values. • The 103Rh (n , 2 n) 102Rh reaction cross sections measurements using activation and offline γ-ray spectrometry method. • Theoretical calculations have been performed using the statistical nuclear reaction TALYS and EMPIRE codes. • The existing cross sections of the 103Rh, 52Cr and 48Ti isotopes were compared with the evaluated and theoretical results. • The nuclear level densities, optical potential and pre-equilibrium models were considered to reproduce the experimental data. • This work will help to overcome discrepancies in existing data and added new experimental data (n , 2 n) in nuclear data library. [ABSTRACT FROM AUTHOR]

The activation cross-sections of 93Nb(n,2n)92Nbm and 88Sr(n,2n)87Srm reactions were measured using the activation and off-line γ-ray spectrometry technique in the neutron energy range 13.97–20.02 MeV. The present measurements have been done at the neutron energies where there are deficiencies and scarcity in the reaction cross-section data. The neutron flux was determined using the 27Al(n,α)24Na monitor reaction. The γ-ray self-attenuation effect and the low energy background neutron corrections were done in this experiment. The results of the present work were compared with the previously published data and evaluated nuclear data libraries. Theoretically, the cross-section for 93Nb(n,2n)92Nbm and 88Sr(n,2n)87Srm reactions was predicted by TALYS-1.9 nuclear code and compared with the present results. • The cross-section of 93Nb(n,2n)92Nbm and 88Sr(n,2n)87Srm reactions were measured in 13.97 to 20.02 MeV neutron energy range. • The comparisons of present results were done with previously published data, evaluated data and theoretically predicted data by TALYS-1.9 code. • The experimental results are in good agreement with the previously published data and are following trend line of evaluated data. • This work filled the gap in cross-sections data for both the reactions. [ABSTRACT FROM AUTHOR]

The cross sections for the 232Th(n,γ) reaction have been measured in the neutron energy range of 11-19 MeV by using activation and offline γ-ray spectrometric techniques. The neutrons of desired energy were obtained by the 7Li(p,n) reaction using a proton beam of 13-21 MeV from the 14UD BARC-TIFR Pelletron facility at Mumbai, India. The 232Th(n,γ) reaction cross sections were calculated using the computer code talys-1.8. The uncertainties in the measurement have been studied using covariance analysis of the experimental data. The results from the present work have been compared with the evaluated data of ENDF/B-VII.1 and JENDL-4.0 as well as the theoretically calculated values based on talys-1.8, and were found to be in good agreement. The outcome of the present work is important for the development of future fast reactors and accelerator driven subcritical systems (ADSs). [ABSTRACT FROM AUTHOR]