Neutron Flux and Spectra Measurements in the Sandia Pulsed Reactor Facility (SPRF)
Description:
Introduction: Neutron measurements were made in the pulsed reactor building and on the safety screen of the pulsed reactor in order to determine the neutron yield of the reactor as a function of (1) distance from the reactor centerline, (2) direction in the reactor building, and (3) position on the reactor safety screen.
Date:
January 1962
Creator:
Buckalew, William H.
Item Type:
Refine your search to only
Report
Partner:
UNT Libraries Government Documents Department