Fatigue and environmentally assisted cracking in light water reactors
Fatigue and stress corrosion cracking (SCC) for low-alloy steel used in piping and in steam generator and reactor pressure vessels have been investigated. Fatigue data were obtained on medium-sulfur-content A533-Gr B and A106-Gr B steels in high-purity (HP) deoxygenated water, in simulated pressurized water reactor water, and in air. Analytical studies focused on the behavior of carbon steels in boiling water reactor (BWR) environments. Crack-growth rates of composite fracture-mechanics specimens of A533-Gr B/Inconel-182/Inconel-600 (plated with nickel) and homogeneous specimens of A533-Gr B steel were determined under small-amplitude cyclic loading in HP water with {approx}300 pbb dissolved oxygen. Radiation-induced segregation and irradiation-assisted SCC of Type 304 SS after accumulation of relatively high fluence also have been investigated. Microchemical and microstructural changes in HP and commercial-purity Type 304 SS specimens from control-blade absorber tubes used in two operating BWRs were studied by Auger electron spectroscopy and scanning electron microscopy, and slow-strain-rate tensile tests were conducted on tubular specimens in air and in simulated BWR water at 289{degrees}C.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 5301908
- Report Number(s):
- ANL/CP-76322; CONF-920375--22; ON: DE92014851
- Country of Publication:
- United States
- Language:
- English
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Environmentally assisted cracking in light water reactors. Semiannual report, April--September 1991: Volume 13
Environmentally assisted cracking in light water reactors. Semiannual report April--September 1992
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
AUSTENITIC STEELS
BOILERS
BWR TYPE REACTORS
CARBON STEELS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
CRYSTAL STRUCTURE
ENRICHED URANIUM REACTORS
FATIGUE
FERRITIC STEELS
FRACTURE MECHANICS
FRACTURE PROPERTIES
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MECHANICS
MICROSTRUCTURE
NICKEL ALLOYS
PIPES
POWER REACTORS
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEAM GENERATORS
STEEL-ASTM-A106
STEEL-ASTM-A533-B
STEEL-CR19NI10
STEELS
STRESS CORROSION
THERMAL REACTORS
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS