Neutron yield in inelastic collisions of 14-Mev neutrons with nuclei and cross section for the (n, 2n) reaction

Autor: Lebedev, P. P., Zysin, Iu. A., Klintsov, Iu. S., Stsiborskii, B. D.
Zdroj: Atomic Energy; November 1958, Vol. 5 Issue: 5 p1431-1434, 4p
Abstrakt: A measurement has been made of ?, the number of neutrons produced in one inelastic scattering event between a neutron and a number of elements of natural isotopic composition: Fe, Cu, Mo, Cd, Sn, Sb, Hg, Pb, Bi and U. The measurements were performed by determining the relative change in the total neutron flux and the attenuation of the primary neutrons after passage through samples of the materials being investigated. It was also possible to obtain data on the cross section sin for inelastic collisions of neutrons with the above-mentioned nuclei. The values of ? and sin, in conjunction with the known cross sections for neutron capture, were then used to compute the cross section for the (n, 2n) reaction (averaged over the isotopic composition) in nonfissile nuclei.
Databáze: Supplemental Index