A METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE

摘要

The intermediate energy neutron flux existing outside the "biological shielding of reactors has not been studied to any great extent previous to this time, due to the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR for the present study utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given.