Measurement of 67Zn(n,p) 67Cu, 64Zn(n,2n) 63Zn, 89Y(n,&gamma,) 90mY and 89Y(n,2n) 88Y Reaction Cross Sections at the Neutron Energy of 14.54 MeV with Covariance Analysis

The 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,&gamma,)90mY and 89Y(n,2n)88Y reaction cross sections relative to the 197Au(n,2n)196Au monitor reaction have been determined at the neutron energy of 14.54 ,± ,0.002 MeV by using the method of activation and off-line &gamma,-ray spectrometry. The neutron energy used was obtained from the 3H(d,n)4He reaction. The covariance analysis was performed by taking the uncertainties arising in various attributes and the correlations between those attributes. The analyzed results from the present measurement were compared with the literature data and evaluated data of various libraries like ENDF/B-VIII, JEFF-3.3, JENDL-4.0 and ROSFOND-2010 libraries as well as with the calculated values based on TALYS-1.9 code

Measurement of 67Zn(n,p) 67Cu, 64Zn(n,2n) 63Zn, 89Y(n,&gamma,) 90mY and 89Y(n,2n) 88Y Reaction Cross Sections at the Neutron Energy of 14.54 MeV with Covariance Analysis

The 67Zn(n,p)67Cu, 64Zn(n,2n)63Zn, 89Y(n,&gamma,)90mY and 89Y(n,2n)88Y reaction cross sections relative to the 197Au(n,2n)196Au monitor reaction have been determined at the neutron energy of 14.54 ,± ,0.002 MeV by using the method of activation and off-line &gamma,-ray spectrometry. The neutron energy used was obtained from the 3H(d,n)4He reaction. The covariance analysis was performed by taking the uncertainties arising in various attributes and the correlations between those attributes. The analyzed results from the present measurement were compared with the literature data and evaluated data of various libraries like ENDF/B-VIII, JEFF-3.3, JENDL-4.0 and ROSFOND-2010 libraries as well as with the calculated values based on TALYS-1.9 code

93Nb(n,2n) 92mNb, 93Nb(n,α) 90mY and 92Mo(n,p) 92mNb Reactions at 14.78 MeV and Covariance Analysis

The cross sections for the 93Nb(n,2n)92mNb, 93Nb(n,α)90mY and the 92Mo(n,p)92mNb reactions have been measured with respect to the 197Au(n,2n)196Au monitor reaction at the incident neutron energy of 14.78 ± 0.19 MeV by employing methods of activation and off-line γ-ray spectrometry. The covariance analysis was carried out by taking into consideration of partial uncertainties in different attributes and correlation among the attributes. The present data have been compared with the literature data available in EXFOR, evaluated data of different libraries and theoretical values based on TALYS-1.8 code

Measurement of Neutron Induced Reaction Cross Sections of Palladium Isotopes at the Neutron Energy of 14.54 ± 0.24 MeV with Covariance Analysis

The 110Pd(n,2n)109Pd, 102Pd(n,2n)101Pd, 105Pd(n,p)105Rh and 106Pd(n,p)106mRh reaction cross sections have been measured with respect to the 197Au(n,2n)196Au monitor reaction at the neutron energy of 14.54 ± 0.24 MeV by using the method of activation and off-line γ-ray spectrometry. The mono-energetic neutron beam was generated from the D–T reaction. The uncertainties in the various basic nuclear parameters in the measured reactions and their correlations were estimated by using covariance analysis. The present data were compared with the EXFOR based literature data, evaluated data of various libraries available in national nuclear data center and with the calculated values from TALYS-1.9 code

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

Measurement of the 240Pu(n,f) cross-section at the CERN n_TOF facility: first results from experimental area II (EAR-2)

The accurate knowledge of the neutron-induced fission cross-sections of actinides and other isotopes involved in the nuclear fuel cycle is essential for the design of advanced nuclear systems, such as Generation-IV nuclear reactors. Such experimental data can also provide the necessary feedback for the adjustment of nuclear model parameters used in the evaluation process, resulting in the further development of nuclear fission models. In the present work, the 240Pu(n,f) cross-section was measured at CERN's n_TOF facility relative to the well-known 235U(n,f) cross section, over a wide range of neutron energies, from meV to almost MeV, using the time-of-flight technique and a set-up based on Micromegas detectors. This measurement was the first experiment to be performed at n_TOF's new experimental area (EAR-2), which offers a significantly higher neutron flux compared to the already existing experimental area (EAR-1). Preliminary results as well as the experimental procedure, including a description of the facility and the data handling and analysis, are presented