Open AccessFracture of Zircaloy cladding by interactions with uranium dioxide pellets in LWR fuel rods. Technical report 10
Author(s) -
E. Smith,
G. V. Ranjan,
R. C. Cipolla
Publication year - 1976
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/7231211
Subject(s) - cladding (metalworking) , zirconium alloy , materials science , pellets , uranium dioxide , corrosion , rod , pellet , nuclear fuel , composite material , metallurgy , stress corrosion cracking , stress (linguistics) , light water reactor , uranium , zirconium , nuclear engineering , medicine , alternative medicine , pathology , engineering , linguistics , philosophy
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