Effects of temperature on fatigue crack growth of a 508-2 steel in LWR environment
Fatigue crack growth rates were determined for A 508-2 steel in pressurized high-temperature, reactor-grade water, over a temperature range of 93/sup 0/C to 288/sup 0/C (200/sup 0/F to 550/sup 0/F). In addition, studies of the oxide layer on the fatigue fracture surface and of the fractography of these specimens were completed in order to provide information on corrosion-assisted, fatigue crack growth mechanisms. The crack growth data show a distinct minimum in growth rate at approx. 200/sup 0/C (approx. 400/sup 0/F). Magnetite (Fe/sub 3/O/sub 4/) was found on the fatigue fracture surfaces at all temperatures. The fractography shows brittle-like features for all test temperatures. These observations suggest that hydrogen evolution may have occurred and that hydrogen-assisted crack growth may be responsible for the environmental effects observed.
- Research Organization:
- Materials Engineering Associates, Inc., Lanham, MD (USA); Valtion Teknillinen Tutkimuskeskus, Espoo (Finland)
- OSTI ID:
- 6272176
- Report Number(s):
- NUREG/CR-3230; MEA-2013; ON: DE83902017
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fatigue-crack growth rates of A 508-2 steel in pressurized, high-temperature water. [PWR]
Temperature dependence of fatigue crack growth rates of A 351 CF8A cast stainless steel in LWR environment
Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
CRACKS
CRYSTAL STRUCTURE
FATIGUE
FRACTURE PROPERTIES
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
MECHANICAL PROPERTIES
MICROSTRUCTURE
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
STEEL-ASTM-A508
STEELS
TEMPERATURE DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS