Optimization of metallurgical variables to improve corrosion resistance of Inconel alloy 600. Final report. [PWR]
Technical Report
·
OSTI ID:5350210
Several aspects of the corrosion performance of thermally treated and mill-annealed Inconel alloy 600 steam generator tubing were evaluated. Thermally treated tubing had caustic stress corrosion cracking (SCC) resistance superior to that of the mill-annealed product over a range of sodium hydroxide concentrations (10 to 50 weight percent), test temperatures (316/sup 0/C to 343/sup 0/C (600/sup 0/F to 650/sup 0/F)), and stress levels. There was a comparable differentiation when specimens were held in the active-passive potential range and in slow strain rate tests in caustic. Corrosion degradation was minimal in both material conditions in high-temperature (332/sup 0/C (630/sup 0/F)) aqueous chloride solutions. SCC was also absent in both material conditions in high-temperature (332/sup 0/C (630/sup 0/F)) aqueous neutral and basic sulfate solutions. However, thermally treated tubing had superior SCC resistance in acid sulfate environments. SCC was present in highly stressed mill-annealed Inconel alloy 600 U-bends exposed to high temperature (360/sup 0/C (680/sup 0/F)) pure water. The SCC initiation time was shorter when the autoclave operated with a hydrogen overpressure.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA)
- OSTI ID:
- 5350210
- Report Number(s):
- EPRI-NP-3051; ON: DE84920007
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effect of carbon content and thermal treatment on the SCC behavior of Inconel Alloy 600 steam generator tubing
Production of eddy-current standards for caustic intergranular corrosion: Final report
Stress corrosion cracking of Alloy 600 and Alloy 690 in all volatile treated water at elevated temperatures. Final report. [PWR]
Journal Article
·
Wed Feb 28 23:00:00 EST 1979
· Corrosion; (United States)
·
OSTI ID:6382003
Production of eddy-current standards for caustic intergranular corrosion: Final report
Technical Report
·
Tue Mar 31 23:00:00 EST 1987
·
OSTI ID:6771727
Stress corrosion cracking of Alloy 600 and Alloy 690 in all volatile treated water at elevated temperatures. Final report. [PWR]
Technical Report
·
Sun May 01 00:00:00 EDT 1983
·
OSTI ID:6278062
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CORROSION
CRACKS
CRYSTAL STRUCTURE
INCONEL 600
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MICROSTRUCTURE
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PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEAM GENERATORS
STRESS CORROSION
STRESSES
TESTING
THERMAL STRESSES
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
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Light-Water Moderated
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36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CORROSION
CRACKS
CRYSTAL STRUCTURE
INCONEL 600
INCONEL ALLOYS
IRON ALLOYS
MATERIALS
MICROSTRUCTURE
NICKEL ALLOYS
NICKEL BASE ALLOYS
NIOBIUM ALLOYS
PERFORMANCE TESTING
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEAM GENERATORS
STRESS CORROSION
STRESSES
TESTING
THERMAL STRESSES
TUBES
VAPOR GENERATORS
WATER CHEMISTRY
WATER COOLED REACTORS
WATER MODERATED REACTORS