Evaluated Neutron-induced Cross Sections for 239Pu and 24°Pu PDF Download
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Languages : en
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Languages : en
Pages : 31
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Using existing experimental data for neutron-induced total, elastic, inelastic, reaction and fission cross sections, as well as results from nuclear model calculations and evaluations from nuclear reaction data libraries, we derived an estimate for the cross sections for the 235U(n,2n) and 239Pu(n,2n) reactions for the neutron energy range from threshold to approximately 12 MeV. In effect, our approach is based on subtracting the fission and inelastic cross sections from the total reaction cross section where the difference is expected to yield the (n,2n) cross section. In addition to this subtraction approach, a ratio method and a differential method have also been explored. For 235U(n,2n), as a test case, we arrive at a cross section consistent with previous measurements, and for 239Pu(n,2n) we obtain a peak value of 400 " 60 mb for the incident neutron energy range of 10 (less-than or equal to) E{sub n} (less-than or equal to) 12 MeV.
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Languages : en
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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.
Author: S. T. Perkins
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Category : Cross sections (Nuclear physics)
Languages : en
Pages : 48
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Author: A. Prince
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Category : Neutron cross sections
Languages : en
Pages : 56
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Author: V.A. Kon'shin
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Category : Capture
Languages : en
Pages : 9
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Languages : en
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Author: R. L. Henkel
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Category : Neutron cross sections
Languages : en
Pages : 28
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Author: David T. Goldman
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Category : Neutron cross sections
Languages : en
Pages : 732
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