Open AccessFission product behavior within two W--UO$sub 2$ cermet fuel elements irradiated in a temperature gradient
Author(s) -
Dirk Seifert,
R.L. Stuart,
P. K. Conn,
H W McLaughlin,
G J Luersen
Publication year - 1968
Language(s) - English
Resource type - Reports
DOI - 10.2172/4309989
Subject(s) - cermet , fission , fission products , nuclear fission product , materials science , irradiation , uranium dioxide , analytical chemistry (journal) , radiochemistry , matrix (chemical analysis) , ceramic , chemistry , uranium , nuclear physics , physics , composite material , metallurgy , neutron , chromatography