Open AccessA METHOD OF DETERMINING THE INTERMEDIATE ENERGY NEUTRON DOSE
Author(s) -
D.E. Hankins
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/4838516
Subject(s) - neutron , neutron temperature , neutron flux , neutron moderator , range (aeronautics) , neutron cross section , nuclear physics , neutron probe , electromagnetic shielding , radiochemistry , energy (signal processing) , physics , materials science , chemistry , quantum mechanics , composite material