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

Conference · Thu Oct 01 04:00:00 EDT 1981 · Corrosion (Houston); (United States)

OSTI ID:7061754

Bulischeck, T S; Van Rooyen, D

Nuclear grade production tubing of Alloy 600 was evaluated for stress corrosion cracking (SCC) susceptibility in high purity water at 365, 345, 325, and 290 C. Reverse tube U-bend specimens provided crack initiation data and constant extension rate tests were employed to determine the crack velocities experienced in th crack propagation stage. Initial results indicate that a linear extrapolation of data received 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.''

• Research Organization: Brookhaven National Lab., Upton, NY
• OSTI ID: 7061754
• Conference Information: Journal Name: Corrosion (Houston); (United States) Journal Volume: 37:10
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105* -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION DENTING
CORROSION PICKLING
CRACK PROPAGATION
DATA
DEFORMATION
EXPERIMENTAL DATA
FAILURES
HEAT TREATMENTS
HIGH TEMPERATURE
INCONEL 600
INCONEL ALLOYS
INFORMATION
IRON ALLOYS
MATERIALS TESTING
MECHANICAL PROPERTIES
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
NUMERICAL DATA
PICKLING
SERVICE LIFE
STEAM GENERATORS
STRESS CORROSION
SURFACE TREATMENTS
TESTING
TUBES
VAPOR GENERATORS