Effect of carbide precipitation on the corrosion behavior of Inconel alloy 690
Conference
·
OSTI ID:7242761
Intergranular carbide precipitation reactions have been shown to affect the stress corrosion cracking (SCC) resistance of nickel-chromium-iron alloys in environments relative to nuclear steam generators. Carbon solubility curves, time-temperature-sensitization plots and other carbide precipitation data are presented for alloy 690 as an aid in developing heat treatments for improved SCC resistance.
- OSTI ID:
- 7242761
- Report Number(s):
- CONF-870314-
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CARBIDES
CARBON COMPOUNDS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION PROTECTION
CORROSION RESISTANCE
CORROSION RESISTANT ALLOYS
CRACKS
FRACTURE MECHANICS
HEAT TREATMENTS
INCONEL 690
INCONEL ALLOYS
INTERGRANULAR CORROSION
KINETICS
MECHANICS
NICKEL ALLOYS
NICKEL BASE ALLOYS
POWER REACTORS
PRECIPITATION
REACTION KINETICS
REACTORS
SEPARATION PROCESSES
STEAM GENERATORS
STRESS CORROSION
TEMPERATURE EFFECTS
VAPOR GENERATORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CARBIDES
CARBON COMPOUNDS
CHEMICAL REACTION KINETICS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION PROTECTION
CORROSION RESISTANCE
CORROSION RESISTANT ALLOYS
CRACKS
FRACTURE MECHANICS
HEAT TREATMENTS
INCONEL 690
INCONEL ALLOYS
INTERGRANULAR CORROSION
KINETICS
MECHANICS
NICKEL ALLOYS
NICKEL BASE ALLOYS
POWER REACTORS
PRECIPITATION
REACTION KINETICS
REACTORS
SEPARATION PROCESSES
STEAM GENERATORS
STRESS CORROSION
TEMPERATURE EFFECTS
VAPOR GENERATORS