Open AccessIN-REACTOR CORROSION BEHAVIOR OF ETCHANT STAINED ZIRCALOY-2.
Author(s) -
E. R. Marx
Publication year - 1971
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/4673862
Subject(s) - zirconium alloy , corrosion , materials science , oxide , hydride , zirconium , cladding (metalworking) , metallurgy , hydrogen , ultimate tensile strength , alloy , metal , chemistry , organic chemistry
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