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THE CORROSION BEHAVIOR OF ZIRCALOY-2 IN 900F STEAM

Author
Andrako, A. M.
Published
United States : [publisher not identified], 1962.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1962.
Physical Description
microopaque : positive ; 8 x 13 cm
Additional Creators
Dearing, B. E.

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Summary
Certified reactor-grade Zircaloy-2 showed extremely erratic corrosion behavior at elevated temperatures (800 to 1200 deg F). This erratic corrosion behavior existed between adjacent samples taken from a rolled strip as well as between samples taken from different strips. An attempt was made to isolate and define the factors affecting this high temperature corrosion behavior. The variability may be due to an extreme sensitivity to sample preparation and/or testing parameters and to small variations in chemical composition, particularly iron and nickel. Specimen shape was found to be an important factor in high temperature evaluations of Zircaloy-2 since edges are subject to preferential attack. The test also showed the danger of extrapolating low temperature Zircaloy-2 corrosion data for high temperature design criteria. (auth)
Report Numbers
KAPL-M-AA-1
Other Subject(s)
Collection
U.S. Atomic Energy Commission depository collection.
Note
DOE contract number: W-31-109-ENG-52
NSA number: NSA-16-017980
OSTI Identifier 4832520
Research organization: Knolls Atomic Power Lab., Schenectady, N.Y.
View MARC record | catkey: 41086985