Open AccessRATES AND MECHANISMS OF THE LOSS OF FISSION PRODUCTS FROM URANIUM-GRAPHITE FUEL MATERIALS
Author(s) -
E A Bryant,
G A Cowan,
J E Sattizahn,
K Wolfsberg
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/4731009
Subject(s) - graphite , nuclear fission product , fission products , porosity , uranium , materials science , fabrication , fission , nuclear fission , radiochemistry , nuclear engineering , chemistry , nuclear physics , metallurgy , composite material , neutron , physics , engineering , medicine , alternative medicine , pathology