Open AccessDEFORMATION AND RUPTURE BEHAVIOR OF LIGHT-WATER REACTOR FUEL CLADDING.
Author(s) -
D.O. Hobson,
P.L. Rittenhouse
Publication year - 1971
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/4734847
Subject(s) - cladding (metalworking) , rod , creep , oxidizing agent , materials science , limiting , atmospheric temperature range , inert , inert gas , light water reactor , irradiation , composite material , chemistry , thermodynamics , nuclear physics , physics , medicine , mechanical engineering , alternative medicine , organic chemistry , pathology , engineering
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