Neutron-photon Multigroup Cross Sections for Neutron Energies Less Than Or Equal to 400 MeV.


Book Description

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.




Neutron-photon Multigroup Cross Sections for Neutron Energies Less Than Or Equal To400 MeV. Revision 1


Book Description

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.




Neutron-photon Multigroup Cross Sections for Neutron Energies [60 MeV.


Book Description

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.