Search

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]

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 measurement of cross-sections producing I n 115 m has been carried out within the energy range of 7–20 MeV. The neutron activation analysis (NAA) followed by off-line γ -ray spectrometry have been used for the purpose. The quasi-monoenergetic neutron beam was produced using the L i (p , n) 7 reaction at the 14UD BARC-TIFR Pelletron accelerator facility at Mumbai, India. The ratio technique of covariance analysis has been used to estimate the uncertainty and correlation between the current experimental data which considers the collective uncertainty from all the attributes in the measurement. The measured cross-sections were compared with the experimental data from the previous literatures, different evaluated data libraries such as ENDF/B-VIII.0, JEFF-3.3, JENDL-4.0, CENDL-3.2 and the theoretically predicted results using the TALYS 1.95 and EMPIRE 3.2.3. The experimental results presented in this work are crucial for the measurement of neutron flux in the NAA technique. • Cross-section of I n (n , n ′) 115 m 115 I n reaction has been measured using the standard neutron activation analysis technique. • The measured cross-sections are compared with results of previous literatures and with the evaluated data libraries. • Theoretical calculations have been performed using nuclear modular code TALYS-1.95 and EMPIRE-3.2.3. • A detailed covariance analysis has been used to measure uncertainties in the measured data. [ABSTRACT FROM AUTHOR]

The production cross sections for the medical isotope 99Mo were measured using the 100Mo(n,2n) reaction at average neutron energies of 10.95±0.45, 13.97±0.68, 16.99±0.53, and 20.00±0.58 MeV using offline γ-ray spectroscopy. The neutron beam was generated using the natLi(p,n) reaction at the 14UD BARC-TIFR Pelletron facility, Mumbai, India. The uncertainties in the measured data were calculated using covariance analysis. The experimental results were compared with the existing data libraries ENDF/B-VII.1, JENDL-4.0, JEFF-3.2, and CENDL-3.1. The present results were also reproduced and compared with the theoretical nuclear model codes talys-1.9 and alice-2017 using different input descriptions. A modified set of parameters were also used in talys-1.9 to fit the existing data more accurately. The present findings show a good agreement with the theoretical predictions and with the existing experimental results from the different data libraries. In addition to this, a comparative study have also been performed between the literature data of (n,p), (n,2n), and (n,a) reaction cross sections at 14.5 MeV using various systematic formulas. The outcomes of the present work are important for the advancement of medical accelerators, dosimetry, and fast reactor systems. [ABSTRACT FROM AUTHOR]