Fast Neutron Flux through the SNAP 10A Shield as Computed by Serveral Methods

摘要

Fast neutron fluxes through the SNAP 10A shield as computed by several methods are compared. The methods and the codes using the methods are: (l) neutron transport - DTK,(2) neutron diffusion - AIM-6, (3) Monte Carlo - FMC-N, and (4) neutron removal theory - l4-0. These various methods predicted fluxes through the shield which agree reasonably well. On the basis of these analyses and recent Shield Test Facility experiments, a lithium hydride removal cross section of 0.156 cm"" is recommended for use in removal theory code studies of the SNAP 1C shield. Comparable analysis of the SNAP 2 shield indicates that a removal cross section of 0.160 cm-1 is valid for use in SNAP 2 shielding studies.