Fast neutron transport in selected materials relevant to large volume minerals analysis

Abstract

The behaviour of the fast neutron flux in a number of materials has been studied for a point source and it has been shown that fluxes computed by using a discrete ordinates code (ANISN) fit a simple exponential form reasonably well. When allowance is made for the collided component in the flux by artificially adjusting the source intensity and energy spectrum it is found that the exponential attenuation form provides an accurate description of the total flux for most materials. Sensitivity factors have been derived which enable elemental concentrations to be obtained when applied to fast neutron induced γ-ray spectra.