Mechanism of fatigue crack initiation in austenitic stainless steels in LWR environments.
Conference
·
OSTI ID:799837
This paper examines the mechanism of fatigue crack initiation in austenitic stainless steels (SSs) in light water reactor (LWR) coolant environments. The effects of key material and loading variables, such as strain amplitude, strain rate, temperature, level of dissolved oxygen in water, and material heat treatment on the fatigue lives of wrought and cast austenitic SSs in air and LWR environments have been evaluated. The influence of reactor coolant environments on the formation and growth of fatigue cracks in polished smooth SS specimens is discussed. Crack length as a function of fatigue cycles was determined in air and LWR environments. The results indicate that decreased fatigue lives of these steels are caused primarily by the effects of the environment on the growth of cracks <200 {micro}m and, to a lesser extent, on enhanced growth rates of longer cracks. A detailed metallographic examination of fatigue test specimens was performed to characterize the fracture morphology. Exploratory fatigue tests were conducted to enhance our understanding of the effects of surface micropits or minor differences in the surface oxide on fatigue crack initiation.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 799837
- Report Number(s):
- ANL/ET/CP-107275
- Country of Publication:
- United States
- Language:
- English
Similar Records
Effect of material heat treatment on fatigue crack initiation in austenitic stainless steels in LWR environments.
Crack initiation in smooth fatigue specimens of austenitic stainless steel in light water reactor environments.
Estimation of fatigue strain-life curves for austenitic stainless steels in light water reactor environments.
Technical Report
·
Sun Jul 31 00:00:00 EDT 2005
·
OSTI ID:925154
Crack initiation in smooth fatigue specimens of austenitic stainless steel in light water reactor environments.
Conference
·
Thu Apr 08 00:00:00 EDT 1999
·
OSTI ID:12388
Estimation of fatigue strain-life curves for austenitic stainless steels in light water reactor environments.
Conference
·
Wed Feb 11 23:00:00 EST 1998
·
OSTI ID:8875