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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Release: 1982
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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.

Evaluation of Neutron Cross Sections to 40 MeV for 54 56Fe

Evaluation of Neutron Cross Sections to 40 MeV for 54 56Fe
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Release: 1980
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Cross sections for neutron-induced reactions on 54 56Fe were calculated by employing several nuclear models: optical, Hauser-Feshbach, preequilibrium and DWBA - in the energy range between 3 and 40 MeV. As a prelude to the calculations, the necessary input parameters were determined or verified through analysis of a large body of experimental data for both neutron- and proton-induced reactions in this mass and energy region. This technique also led to cross sections in which the simultaneous influence of available data types added to their consistency and reliability. Calculated cross sections as well as neutron and gamma-ray emission spectra were incorporated into an ENDF evaluation suitable for use to 40 MeV. 12 figures, 1 table.

Energy Research Abstracts

Energy Research Abstracts
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Total Pages: 840
Release: 1990
Genre: Power resources
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Energy Research Abstracts

Energy Research Abstracts
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Total Pages: 738
Release: 1983
Genre: Power resources
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Includes all works deriving from DOE, other related government-sponsored information and foreign nonnuclear information.

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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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 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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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.

Calculation of Neutron Cross Sections on Iron Between 3 and 40 MeV. [Hauser-Feshbach Model].

Calculation of Neutron Cross Sections on Iron Between 3 and 40 MeV. [Hauser-Feshbach Model].
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Release: 1979
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The use of high energy d+Li sources to produce neutrons for radiation damage studies will require evaluated neutron cross sections up to energies of 40 MeV. Experimental data in this energy region are scarce, and reliance must be placed upon nuclear model calculations to provide the necessary cross sections. We have thus calculated neutron-induced cross sections on 54Fe and 56Fe between 3 and 40 MeV using the multistep preequilibrium Hauser-Feshbach model code GNASH. Special care was taken in the determination of optical model parameters applicable over this wide energy range through use of, and comparison to, neutron total cross section and elastic angular distribution data, (p, n), and (.cap alpha., n) data, as well as other high energy proton induced reaction cross sections and spectral results. The preequilibrium-statistical calculations using these parameters as well as gamma-ray strength functions, level densities, and discrete level information reproduce well most available experimental measurements above 3 MeV for varied reaction types including gamma-ray production data. 12 references.

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.