Effects of temperature on fatigue crack growth of A508-2 in LWR environment
Fatigue crack growth rates were determined for A5082 material 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 about200/sup 0/C ( about400/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
- OSTI ID:
- 5315289
- Report Number(s):
- CONF-830607-
- Journal Information:
- Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States), Journal Name: Am. Soc. Mech. Eng., Pressure Vessels Piping Div., (Tech. Rep.) PVP; (United States) Vol. PVP-VOL. 71; ISSN AMPPD
- Country of Publication:
- United States
- Language:
- English
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BRITTLENESS
CHALCOGENIDES
CORROSION FATIGUE
CRACK PROPAGATION
EMBRITTLEMENT
FATIGUE
FRACTOGRAPHY
HYDROGEN COMPOUNDS
HYDROGEN EMBRITTLEMENT
IRON ALLOYS
IRON BASE ALLOYS
IRON COMPOUNDS
IRON ORES
IRON OXIDES
MAGNETITE
MATERIALS
MECHANICAL PROPERTIES
MINERALS
ORES
OXIDE MINERALS
OXIDES
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTOR MATERIALS
REACTORS
SCALING
STEEL-ASTM-A508
STEELS
TEMPERATURE EFFECTS
THERMAL FATIGUE
TRANSITION ELEMENT COMPOUNDS
WATER
WATER COOLED REACTORS
WATER MODERATED REACTORS