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Stress corrosion cracking of alloy 600 using the constant strain rate test

Journal Article · · Corrosion (Houston); (United States)
DOI:https://doi.org/10.5006/1.3577544· OSTI ID:5336953
; ;
Nuclear grade tubing was evaluated in high purity water at 365, 345, 325, and 290 C. Initial results indicate that a linear extrapolation of data from high temperature tests can be used to predict the service life of steam generator tubing that has been plastically deformed or is continually deforming by denting. 8 refs.
Research Organization:
Assoc Univ Inc, Upton, NY, USA
OSTI ID:
5336953
Journal Information:
Corrosion (Houston); (United States), Journal Name: Corrosion (Houston); (United States) Vol. 37:10; ISSN CORRA
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CRACK PROPAGATION
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
PIPES
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS