Treatment of Alloy 600 tube-tube sheet transitions for improved resistance to primary water SCC I. Performance of baseline as-expanded samples in 750/sup 0/F steam
Mill annealed Alloy 600 tubing samples were mechanically expanded (hard rolled) into steel collars using standard manufacturing techniques. The rolled specimens contained transitions from unexpanded to expanded tubing that were representative of those in as-fabricated nuclear steam generators. A specially fabricated heat of Alloy 600 tubing in two standard sizes was used. This special tubing exhibited a high susceptibility to primary water stress corrosion cracking (PWSCC) in tests of reverse U-bends in 750/sup 0/F (400/sup 0/C) steam with hydrogen. The expanded samples were shown in relatively prolonged exposures to the steam condition to develop axial intergranular stress corrosion cracks on the inner tube surfaces in the transition regions. It is concluded that the samples and the steam condition constitute a useful combination in evaluating the benefits of treatments to improve the PWSCC resistance of as-expanded mill annealed Alloy 600 transitions.
- OSTI ID:
- 6976957
- Report Number(s):
- CONF-870314-
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
360103 -- Metals & Alloys-- Mechanical Properties
360105* -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION PROTECTION
CORROSION RESISTANCE
CORROSIVE EFFECTS
CRACKS
ELEMENTS
FABRICATION
FRACTURE MECHANICS
HIGH TEMPERATURE
HYDROGEN
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS WORKING
MECHANICS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
NONMETALS
POWER REACTORS
REACTORS
ROLLING
SHEETS
SLEEVES
STEAM
STEAM GENERATORS
STRESS CORROSION
TUBES
VAPOR GENERATORS