Open Access
POST-IRRADIATION EXAMINATION OF ZIRCALOY-2- AND INCOLOY-800-CLAD FUEL RODS IRRADIATED TO 7000 MWd/TU IN THE CONSUMERS BIG ROCK POINT REACTOR.
Author(s) -
V.E. Hazel
Publication year - 1968
Language(s) - English
Resource type - Reports
DOI - 10.2172/4492212
Subject(s) - pellets , rod , incoloy , materials science , irradiation , pellet , nuclear engineering , zirconium alloy , composite material , radiochemistry , nuclear physics , chemistry , engineering , physics , medicine , alternative medicine , alloy , pathology