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:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10150189
- Report Number(s):
- ANL/CP--76322; CONF-920375--22; ON: DE92014851
- Country of Publication:
- United States
- Language:
- English
Similar Records
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
Related Subjects
210100
210200
36 MATERIALS SCIENCE
360103
BWR TYPE REACTORS
CARBON STEELS
CRACK PROPAGATION
CRACKS
FATIGUE
FERRITIC STEELS
FRACTURE MECHANICS
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
MICROSTRUCTURE
PIPES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PRESSURE VESSELS
PWR TYPE REACTORS
RADIATION EFFECTS
REACTOR COMPONENTS
STAINLESS STEEL-304
STEAM GENERATORS
STEEL-ASTM-A106
STEEL-ASTM-A533-B
STEELS
STRESS CORROSION