Calculated Neutron-induced Cross Sections for /sup 53/Cr from 1 to 20 MeV.

Calculated Neutron-induced Cross Sections for /sup 53/Cr from 1 to 20 MeV.
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Release: 1987
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Neutron-induced cross sections of /sup 53/Cr have been calculated in the energy regions from 1 to 20 MeV. The quantities obtained are the cross sections for the reactions (n, n'.gamma.), (n,2n), (n, np), (n, n.cap alpha.), (n, p.gamma.), (n, pn), (n, .cap alpha gamma.), (n, .cap alpha.n), (n, d), (n, t), (n, /sup 3/He), and (n, .gamma.), as well as the spectra of emitted neutrons, protons, alpha particles, and gamma rays. The precompound process was included above 5 MeV in addition to the compound process. For the inelastic scattering, the contribution of the direct interaction was calculated with DWBA. 36 refs., 23 figs., 11 tabs.

Calculated Neutron-induced Cross Sections for /sup 52/Cr from 1 to 20 MeV and Comparisons with Experiments

Calculated Neutron-induced Cross Sections for /sup 52/Cr from 1 to 20 MeV and Comparisons with Experiments
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Release: 1987
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ISBN:

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Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 52/Cr for incident energies from 1 to 20 MeV. The input parameters for the model codes were determined through analysis of experimental data in this energy region. Discussion of the models used, the input data, the resulting calculations, extensive comparisons to measured data, and comparisons to the Evaluated Nuclear Data File (ENDF/B-V) for Cr (MAT 1324) are included in this report. 103 refs., 67 figs., 12 tabs.

Calculated Neutron-induced Cross Sections for /sup 58,60/Ni from 1 to 20 MeV and Comparisons with Experiments

Calculated Neutron-induced Cross Sections for /sup 58,60/Ni from 1 to 20 MeV and Comparisons with Experiments
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Release: 1987
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Nuclear model codes were used to compute cross sections for neutron-induced reactions on both /sup 58/Ni and /sup 60/Ni for incident energies from 1 to 20 MeV. The input parameters for the model codes were determined through analysis of experimental data in this energy region. Discussion of the models used, the input data, the resulting calculations, extensive comparisons to measured data, and comparisons to the Evaluated Nuclear Data File (ENDF/B-V) for Ni (MAT 1328) are included in this report. 118 refs., 101 figs., 19 tabs.

Neutron Cross Sections

Neutron Cross Sections
Author: Victoria McLane
Publisher: Elsevier
Total Pages: 850
Release: 2012-12-02
Genre: Science
ISBN: 0323142222

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Neutron Cross Sections, Volume 2: Neutron Cross Section Curves presents data for total reaction cross sections and related fission parameters as a function of incident-neutron energy. This book covers energy range from 0.01 eV to 200 MeV to exclude crystalline and magnetic effects for slow neutrons and relativistic effects for high energy neutrons. The data in this volume are grouped into sections corresponding to the element of the target nucleus in the neutron-induced reaction. These sections are ordered in increasing atomic number. Within a section, graphical data are presented for the natural element followed by the isotopes of that element in order of increasing atomic mass. A list of the reaction types is provided at the end of each section. This book also provides graphical section, wherein each graphical page is annotated on the outer edge with a symbol for an element or isotope followed by the list of the cross section data for that element or isotope. The data plotted in the graphical section are tagged by a mnemonic consisting of year, laboratory, and author's last name. This tag can be used to find the corresponding reference on the bibliographic pages.

Calculated Cross Sections for Neutron Induced Reactions on Sup 19 F and Uncertainties of Parameters

Calculated Cross Sections for Neutron Induced Reactions on Sup 19 F and Uncertainties of Parameters
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Total Pages: 73
Release: 1990
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ISBN:

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Nuclear model codes were used to calculate cross sections for neutron-induced reactions on 19F for incident energies from 2 to 20 MeV. The model parameters in the codes were adjusted to best reproduce experimental data and are given in this report. The calculated results are compared to measured data and the evaluated values of ENDF/B-V. The covariance matrix for several of the most sensitive model parameters is given based on the scatter of measured data around the theoretical curves and the long-range correlation error of measured data. The results of these calculations form the basis for the new ENDF/B-VI fluorine evaluation. 44 refs., 64 figs., 14 tabs.

Calculated Neutron-induced Cross Sections for

Calculated Neutron-induced Cross Sections for
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Release: 1985
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ISBN:

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Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 63,65/Cu, /sup 58,60/Ni, and 52Cr for incident energies from 1 to 20 MeV. The input parameters for the model codes determined through analysis of experimental data in this energy region. The models used, the input data, the resulting calculations, and comparisons with measured data are discussed. 15 refs.