Measurement of 14.54 MeV Neutron Induced Reaction Cross Sections of Cr and Mn with Covariance Analysis

The 50Cr(n,2n)49Cr, 52Cr(n,2n)51Cr, 52Cr(n,p)52V, 55Mn(n,2n)54Mn, 55Mn(n,α)52V and 55Mn(n,γ)56Mn reaction cross sections at the neutron energy of 14.54 ± 0.24 MeV were measured by using activation method along with off-line γ-ray spectrometry. The 27Al(n,p)27Mg monitor reaction was used for the 52Cr(n,p)52V and 55Mn(n,α)52V reactions, whereas the 197Au(n,γ)198Au monitor reaction for the 55Mn(n,γ)56Mn reaction. The 27Al(n,α)24Na monitor reaction was used for other three reactions. The neutron beam was generated from the T(d,n)4He reaction using the Purnima neutron generator at BARC, Mumbai. The covariance analysis for the uncertainties of reaction cross sections was performed by considering the correlations between different attributes. The present results were compared with the literature data, evaluated data of ENDF, ROSFOND, CENDL, JENDL and JEFF libraries as well as with the theoretical values based on TALYS-1.9 calculation

Measurement of 14.54 ± 0.24 MeV Neutron Activation Reaction Cross Sections of 93Nb, natMo with Covariance Analysis

The 93Nb(n,α)90mY, 93Nb(n,2n)92mNb and 92Mo(n,p)92mNb reaction cross sections have been measured relative to the 197Au(n,2n)196Au monitor reaction at the neutron energy of 14.54 ± 0.24 MeV. The neutrons were generated from the T(d,n)4He reaction using Purnima neutron generator. The experiment was done by using the method of activation in combination with an off-line γ\documentclass[12pt]{minimal}\usepackage{amsmath}\usepackage{wasysym}\usepackage{amsfonts}\usepackage{amssymb}\usepackage{amsbsy}\usepackage{mathrsfs}\usepackage{upgreek}\setlength{\oddsidemargin}{-69pt}\begin{document}$$\gamma$$\end{document}-ray spectrometry technique. The uncertainties and correlations for the reaction cross sections were estimated with the use of covariance analysis by considering the partial uncertainties in individual attributes. The measured reaction cross sections have been analyzed by comparing with the data available in EXFOR compilation, various files of evaluated data and theoretically calculated values from TALYS-1.9