Irradiation effects on grain boundary chemistry of austenitic stainless steels
- Battelle Pacific Northwest Lab., Richland, WA (United States)
Parametric studies of radiation-induced segregation (RIS) at internal interfaces in austenitic stainless steels have been performed for the first time. The current approach analyzes ion-irradiated, microcrystalline materials and provides a statistical evaluation of irradiation effects on interfacial composition. Measurements document irradiation fluence and temperature effects on RIS. Grain boundary enrichment of nickel and silicon, and depletion of chromium, iron and molybdenum, are established after irradiation. Impurities such as phosphorus and sulfur were not detected even though phosphorus-doped stainless steels were examined. Results raise questions concerning the application of existing models to predict grain boundary segregation. A distinct boundary-to-boundary variation in microchemistry is observed which cannot be explained by traditional non-equilibrium segregation theory. Existing RIS theories are based on surface segregation measurements. No detailed studies of RIS to internal interfaces has been performed. The use of sputter-deposited microcrystalline materials and ion irradiation enables parametric studies of bulk behavior to be performed in a timely and inexpensive method. Detailed investigations of material and irradiation effects on RIS to, and precipitation at, internal interfaces are now possible.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (United States); Battelle Pacific Northwest Lab., Richland, WA (United States)
- Sponsoring Organization:
- EPRI; Electric Power Research Inst., Palo Alto, CA (United States)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 5283955
- Report Number(s):
- EPRI-TR-100548
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
360102 -- Metals & Alloys-- Structure & Phase Studies
360105 -- Metals & Alloys-- Corrosion & Erosion
360106 -- Metals & Alloys-- Radiation Effects
ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CORROSION
CORROSION RESISTANT ALLOYS
CRYSTAL STRUCTURE
ELECTRON MICROSCOPY
ENRICHED URANIUM REACTORS
GRAIN BOUNDARIES
HEAT RESIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
INTERGRANULAR CORROSION
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MICROSCOPY
MICROSTRUCTURE
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PHYSICAL RADIATION EFFECTS
POWER REACTORS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR MATERIALS
REACTORS
SEGREGATION
SPUTTERING
STAINLESS STEEL-304
STAINLESS STEEL-316
STAINLESS STEELS
STEEL-CR17NI12MO3
STEEL-CR19NI10
STEELS
STRESS CORROSION
THERMAL REACTORS
TRANSMISSION ELECTRON MICROSCOPY
WATER COOLED REACTORS
WATER MODERATED REACTORS