Fatigue crack growth of A508 steel in high-temperature, pressurized reactor grade water
Fatigue crack growth tests of A508-2 pressure vessel steel have been conducted at two test temperatures(93 C and 288 C) using a variety of constant amplitude waveforms. The load ratios were either 0.1 or 0.125, and the water chemistry was carefully monitored and controlled so as to simulate the nominal pressurized water reactor chemistry. The test procedures are described, and an examination of all the data indicates that the results fall into one of two rather clearly defined categories. One band of data, termed 'low', lies close to or essentially on, the ASME Section XI Code air environment default line. The other band of data, termed 'high', resides approximately midway between the ASME Sec. XI air and water environment default lines.
- Research Organization:
- Naval Research Lab., Washington, DC (USA)
- OSTI ID:
- 5489751
- Report Number(s):
- NUREG/CR-0969
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103* -- Metals & Alloys-- Mechanical Properties
ALLOYS
CHEMICAL REACTIONS
CONTAINERS
CORROSION
CRACKS
CRYOGENIC FLUIDS
ELEMENTS
EMBRITTLEMENT
FATIGUE
FLUIDS
FRACTOGRAPHY
HIGH TEMPERATURE
HYDROGEN
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
METALLOGRAPHY
NONMETALS
PRESSURE VESSELS
REACTOR MATERIALS
STEEL-ASTM-A508
STEELS
STRESS CORROSION