Strain Rate Effects on the Fatigue Crack Growth of SA508 Cl.3 Reactor Pressure Vessel Steel in High-Temperature Water Environment

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Corrosion fatigue tests were performed in air saturated hot water to assess fatigue crack growth behavior of reactor pressure vessel steel at the LWR operating condition. The main test parameter H as loading frequency. Crack growth rare was increased with decreasing frequency until a critical frequency. It M as found through fractographic study that the enhancement of crack growth rate was environmentally assisted by the hydrogen embrittlement, since brittle striations and cleavagelike facets with microvoid were formed in the crack growth process. The strain rate effects on crack growth rate were investigated through da/dt versus d epsilon /dt curves. At intermediate range, there is a transient point which corresponds to an onset of dynamic strain aging and abruptly increases the crack growth rare: above the transient point. small-size-particle-enhanced brittle cracks, while only large-size-particle-enhanced brittle cracks before the transient. From the fractography, it is suggested that EAC may be enhanced by specific strain rate, and that EAC may be related to interactions of hydrogen with oxide film and to Luders band movement with a high strain gradient at inclusion/matrix interface.
Publisher
Asme-Amer Soc Mechanical Eng
Issue Date
2001-05
Language
English
Article Type
Article; Proceedings Paper
Keywords

LOW-ALLOY STEELS; ASSISTED CRACKING; HYDROGEN

Citation

JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, v.123, no.2, pp.173 - 178

ISSN
0094-9930
URI
http://hdl.handle.net/10203/80783
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