Neutron-photon Multigroup Cross Sections for Neutron Energies Up to 400 Mev
Author : Hiroshi Kotegawa
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Page : 25 pages
File Size : 34,15 MB
Release : 1993
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Author : Hiroshi Kotegawa
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Page : 25 pages
File Size : 34,15 MB
Release : 1993
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Author :
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Page : pages
File Size : 47,97 MB
Release : 1981
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Multigroup cross sections (66 neutron groups and 21 gamma ray groups) are described for neutron energies from thermal to 400 MeV. The elements considered are hydrogen, /sup 10/B, /sup 11/B, carbon, nitrogen, oxygen, sodium, magnesium, aluminum, silicon, sulfur, potassium, calcium, chromium, iron, nickel, tungsten and lead. These cross sections are available from the Radiation Shielding Information Center of the Oak Ridge National Laboratory. 19 references.
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Page : pages
File Size : 20,1 MB
Release : 1986
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Multigroup cross sections (66 neutron groups and 22 photon groups) are described for neutron energies from thermal to 400 MeV. The elements considered are hydrogen, /sup 10/B, /sup 11/B, carbon, nitrogen, oxygen, sodium, magnesium, aluminum, silicon, sulfur, potassium, calcium, chromium, iron, nickel, tungsten, and lead. The cross section data presented are a revision of similar data presented previously. In the case of iron, transport calculations using the earlier and the revised cross sections are presented and compared, and significant differences are found. The revised cross sections are available from the Radiation Shielding information Center of the Oak Ridge National Laboratory. 32 refs., 5 figs., 3 tabs.
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Page : pages
File Size : 19,99 MB
Release : 1978
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Multigroup cross sections (47 n-groups, 21 .gamma.-groups) in ANISN format for neutron energies from thermal to 60 MeV and for the elements H, /sup 10/B, /sup 11/B, C, O, Si, Ca, Cr, Fe, and Ni are described. A P/sub 5/-Legendre expansion is used at energies equal to or greater than 14.9 MeV and a P/sub 3/-Legendre expansion is used at energies equal to or less than 14.9 MeV. Calculated results of the dose equivalent vs. depth in the shield from a point isotropic source at the center of a spherical shell (366 cm thick) heavy-concrete (density = 3.6 g cm/sup -3/) shield are presented. The energy distribution of the source neutrons is approximately that from a Li(D, n) neutron radiation damage facility.
Author : R. G. Alsmiller
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Page : 33 pages
File Size : 43,51 MB
Release : 1978
Category : Neutron cross sections
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Author : David T. Goldman
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Page : 736 pages
File Size : 50,10 MB
Release : 1968
Category : Neutron cross sections
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Author : Nunzio Tralli
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Page : 218 pages
File Size : 50,41 MB
Release : 1958
Category : Neutron cross sections
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Author : Robert J. Howerton
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Page : 28 pages
File Size : 34,78 MB
Release : 1958
Category : Elastic scattering
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Author : M. R. Bhat
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Page : 440 pages
File Size : 40,60 MB
Release : 1980
Category : Fast neutrons
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Author :
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Page : 150 pages
File Size : 27,66 MB
Release : 1962
Category : Neutron cross sections
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