The 112Cd(n,2n)111mCd and 112Cd(n,p)112Ag reaction cross sections have been measured at the neutron energy of 14.54 ± 0.24 MeV by using the method of activation and off-line γ -ray spectroscopy. The mano-energetic neutrons were obtained from the D–T reaction using the Purnima Neutron Generator at BARC. The 197Au(n,2n)196Au and115In(n, n1)115mIn reactions were used for neutron flux monitors. The covariance analysis for the uncertainties in the measured reaction cross sections has been done based on various uncertained attributes. The experimental values were compared with the theoritically calculated values from TALYS-1.95 code, evaluated data from different libraries and literature data based on EXFOR compilation.

The cross sections have been estimated for the Nuclear reactions Mo-92(n,a)Zr-89 and Mo-97(n,p)Nb-97 produced in Purnima neutron generator at neutron energy of 13.52 +/- 0.0045 MeV using activation analysis and off-line gamma-ray spectrometric techniques. Al-27(n,alpha)Na-24 has been used as a monitor reaction. The covariance analysis for these cross sections has been carried out by taking into consideration of partial uncertainties of different attributes and correlations between the attributes. The cross section values of the present study have been compared with EXFOR, ENDF data of various libraries and theoretical data of TALYS-1.8 code.

The 115 In(n,2n) 114m In and 197 Au(n,2n) 196 Au reaction cross sections have been measured relative to the 27 Al(n,α) 24 Na monitor reaction at the two different incident neutron energies of 13.520 ± 0.005 MeV and 14.54 ± 0.24 MeV. The neutrons from the D-T fusion reaction at the Purnima neutron generator were used for activation followed by off-line γ-ray spectrometry. The uncertainty propagation and correlation of measured reaction cross sections were estimated using covariance analysis through considering the partial uncertainties in different attributes. The measured reaction cross sections from the present work have been compared with the literature data from EXFOR compilation, ENDF data of various libraries and theoretically calculated values from the TALYS-1.9 code.

The (n,2n) reaction cross sections of cerium isotopes have been experimentally measured at the neutron energy of 13.50 ± 0.15 MeV by using the method of activation and off-line γ-ray spectroscopy. The neutron energy was obtained from the D-T reaction using the Purnima Neutron Generator at BARC. The natCe sample was irradiated along with the gold and indium monitor foils. The cross sections of 140Ce(n,2n)139Ce and 142Ce(n,2n)141Ce reactions were measured by using both the gold and indium as a monitor and then collapsed to get the best values of reactions cross sections. The uncertainties in the measured cross sections of 140Ce(n,2n)139Ce and 142Ce(n,2n)141Ce reactions were determined using covariance analysis by considering uncertainties in various attributes. The measured values from the present work were compared with the literature data based on EXFOR compilation, evaluated data from different libraries and theoretically calculated values from TALYS-1.95 and EMPIRE-3.2.

The 115In(n,2n)114mIn and 197Au(n,2n)196Au reaction cross sections have been measured relative to the 27Al(n,α)24Na monitor reaction at the two different incident neutron energies of 13.520 ± 0.005 MeV and 14.54 ± 0.24 MeV. The neutrons from the D-T fusion reaction at the Purnima neutron generator were used for activation followed by off-line γ-ray spectrometry. The uncertainty propagation and correlation of measured reaction cross sections were estimated using covariance analysis through considering the partial uncertainties in different attributes. The measured reaction cross sections from the present work have been compared with the literature data from EXFOR compilation, ENDF data of various libraries and theoretically calculated values from the TALYS-1.9 code.

The 92Mo(n,α)89Zr, 97Mo(n,p)97Nb, 148Nd(n,2n)147Nd and 146Nd(n,p)146Pr reaction cross sections with the neutron of energy of 14.54 ± 0.24 MeV have been measured by using the method of activation and off-line γ-ray spectrometry. The neutron was generated from the D-T reaction at the PURNIMA neutron generator of BARC. The 197Au(n,2n)196Au monitor reaction was used for the estimation of neutron flux. The covariance analysis for the uncertainties of the cross sections has been carried out by considering the partial uncertainties of different attributes. The present data have been compared with the literature data, evaluated data and theoretically calculated values from TALYS-1.9 code.