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Calculation of 235U(n, N') Cross Sections for ENDF

Calculation of 235U(n, N') Cross Sections for ENDF
Author:
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Total Pages:
Release: 1988
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ISBN:

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Cross sections for neutron-induced reactions on 235U between 0.01 and 20 MeV have been calculated in a preliminary analysis for the ENDF/B-VI evaluation with particular emphasis on neutron inelastic scattering. A deformed optical model potential that fits total, elastic, inelastic, and low-energy average resonance data is used to calculate direct (n, n') cross sections and transmission coefficients for a Hauser-Feshbach statistical theory analysis using a multiple fission barrier representation. Direct cross sections for higher-lying vibrational states are provided from DWBA calculations, normalized using B(E/ital l/) values determined from (d, d') and Coulomb excitation data. Initial fission barrier parameters and transition state density enhancements appropriate to the compound systems involved were obtained from previous analyses, especially fits to charged-particle fission probability data. Further modifications to fit 235U(n, f) data were small, and the final fission parameters are generally consistent with published values. The results from this preliminary analysis are compared with the ENDF/B-V evaluation as well as with experimental data. 26 refs., 5 figs., 3 tabs.


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
Author:
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.


Program GROUPLE (version 79-1)

Program GROUPLE (version 79-1)
Author: Dermott Edward Cullen
Publisher:
Total Pages: 76
Release: 1980
Genre: GROUPLE (Computer program)
ISBN:

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Nuclear Cross Sections and Technology

Nuclear Cross Sections and Technology
Author: Roald A. Schrack
Publisher:
Total Pages: 564
Release: 1975
Genre: Cross sections (Nuclear physics)
ISBN:

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Testing New Actinide Cross Sections Proposed for ENDF

Testing New Actinide Cross Sections Proposed for ENDF
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Total Pages: 7
Release: 2004
Genre:
ISBN:

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Our Nuclear Physics Group has worked over the last several years to improve the ENDF/B actinide cross sections, especially as measured against the famous series of fast-spectrum critical experiments performed at Los Alamos under such names as Godiva, Jezebel, the Flattops, and Bigten. The new evaluations include changes in the high-energy fission cross sections, nubar, elastic scattering, inelastic scattering, fission spectra, and delayed neutrons that combine to significantly improve the calculated results for the Los Alamos critical assemblies. As a happy byproduct of this work, we found that the new evaluations also removed about half of a long-standing discrepancy in calculations of thermal-reactor critical experiments using lattices of low-enriched uranium oxide rods. In the meantime, work at the Oak Ridge National Laboratory has resulted in new proposed resonance parameters for U238. When these low-energy data are combined with the new high-energy data from Los Alamos, they have the effect of removing most of the rest of the problem for thermal lattices. Although more work will be done at both Los Alamos and Oak Ridge, including making the evaluations consistent with the new standards, the results presented in this talk provide promise that ENDF/B-VII will result in good improvements for users at both high and low neutron energies.


Nuclear Cross Sections for Technology

Nuclear Cross Sections for Technology
Author: Joseph L. Fowler
Publisher:
Total Pages: 1060
Release: 1980
Genre: Cross sections (Nuclear physics)
ISBN:

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Evaluation Of[sup 28,29,30]i Neutron Induced Cross Sections for ENDF/B-VI.

Evaluation Of[sup 28,29,30]i Neutron Induced Cross Sections for ENDF/B-VI.
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Release: 2001
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Separate evaluations have been done for the three stable isotopes of silicon for ENDF/B-VI. The evaluations are based on analysis of experimental data, supplemented by results of nuclear model calculations. The computational methods and the parameters required as input to the nuclear model codes are reviewed. Discussion of the evaluated data given for resonance parameters, neutron induced reaction cross sections, associated angular and energy distributions, and gamma-ray production cross sections is included. Extensive comparisons of the evaluated cross sections to measured data are shown in this report. The evaluations include all necessary data to allow KERMA (Kinetic Energy Released in MAterials) and displacement cross sections to be calculated directly. These quantities are fundamental to studies of neutron heating and radiation damage.