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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Total Pages:
Release: 1987
Genre:
ISBN:

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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.

Nuclear Cross Sections for 95-Mev Neutrons

Nuclear Cross Sections for 95-Mev Neutrons
Author: James DeJuren
Publisher:
Total Pages: 24
Release: 1950
Genre: Bismuth
ISBN:

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The total cross sections of twelve different elements were measured using the neutron beam from the 184-in. cyclotron, operating with deuterons. Bismuth fission ionization chambers were employed as both monitor and detector in conventional 'good geometry' attenuation measurements in the neutron flux emerging from the 3-in. diameter collimating port in the 10-ft-thick concrete shielding. The mean energy of detection of the neutrons in this experiment is estimated to be 95 Mev. Measurements were also made with a monitor and detector placed inside the concrete shielding where an intense neutron flux over a large area could be obtained. Attenuators of four different elements were placed in front of the detector in a 'poor geometry' arrangement so that attenuation was due essentially to inelastic collisions which degrade the neutron energy below the fission threshold. A second detector was placed outside the concrete shielding In the collimated neutron beam in line with the neutron source, absorber, and first detector. Attenuation in it is caused by both inelastic and elastic scattering. By this arrangement the ratio of inelastic to total cross section can be determined directly in one experiment. The nuclear radii as calculated from the observed cross section, using the theory of the transparent nucleus, vary as 1.38 x 10(exp-13) A(exp(1/3)) cm. In this energy range the ratios of the inelastic to total cross sections are all less than one-half.

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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Publisher:
Total Pages: 73
Release: 1990
Genre:
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 /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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ISBN:

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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.

Evaluated Neutron-induced Cross Sections for /sup 40/Ca from 20 to 40 MeV.

Evaluated Neutron-induced Cross Sections for /sup 40/Ca from 20 to 40 MeV.
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Total Pages:
Release: 1982
Genre:
ISBN:

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Nuclear model codes were used to compute cross sections for neutron-induced reactions on /sup 40/Ca for incident energies from 20 to 40 MeV. The input parameters for the model codes were determined through analysis of experimental data in this energy region. Computed cross sections along with emission spectra for each product were combined into an Evaluated Nuclear Data File (ENDF) using the proposed format for charged-particle reactions. Discussion of the models used, the resulting calculations, and the final evaluated data file are presented.

Calculated Neutron-induced Cross Sections for

Calculated Neutron-induced Cross Sections for
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Total Pages:
Release: 1985
Genre:
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.