Open AccessReview of in-reactor zircaloy corrosion and crud deposition experience at AECL
Author(s) -
V.F. Urbanic,
R.G. Gray,
D. H. Lister
Publication year - 1979
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/5426946
Subject(s) - corrosion , cladding (metalworking) , coolant , zirconium alloy , materials science , metallurgy , zirconium , nuclear engineering , pressurized water reactor , nuclear physics , engineering , physics
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