Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Conference
·
OSTI ID:10144367
Both temperature and oxygen affect fatigue life; at the very low dissolved-oxygen levels in PWRs and BWRs with hydrogen water chemistry, environmental effects on fatigue life are modest at all temperatures (T) and strain rates. Between 0.1 and 0.2 ppM, the effect of dissolved-oxygen increases rapidly. In oxygenated environments, fatigue life depends strongly on strain rate and T. A fracture mechanics model is developed for predicting fatigue lives, and interim environmentally assisted cracking (EAC)-adjusted fatigue curves are proposed for carbon steels, low-alloy steels, and austenitic stainless steels.
- Research Organization:
- Argonne National Lab., IL (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 10144367
- Report Number(s):
- ANL/MCT/CP-78588; CONF-921007-23; ON: DE93009202
- Resource Relation:
- Conference: 20. water reactor safety information meeting,Bethesda, MD (United States),21-23 Oct 1992; Other Information: PBD: Jan 1993
- Country of Publication:
- United States
- Language:
- English
Similar Records
Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Conference
·
Fri Jan 01 00:00:00 EST 1993
·
OSTI ID:10144367
Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Technical Report
·
Thu Apr 01 00:00:00 EST 1993
·
OSTI ID:10144367
Interim fatigue design curves for carbon, low-alloy, and austenitic stainless steels in LWR environments
Technical Report
·
Thu Apr 01 00:00:00 EST 1993
·
OSTI ID:10144367
Related Subjects
36 MATERIALS SCIENCE
22 GENERAL STUDIES OF NUCLEAR REACTORS
CARBON STEELS
FATIGUE
LOW ALLOY STEELS
STAINLESS STEELS
AUSTENITIC STEELS
PWR TYPE REACTORS
BWR TYPE REACTORS
FRACTURE MECHANICS
CRACK PROPAGATION
OXYGEN
STRAIN RATE
TEMPERATURE RANGE 0400-1000 K
RECOMMENDATIONS
CORRELATIONS
360103
220200
MECHANICAL PROPERTIES
COMPONENTS AND ACCESSORIES
22 GENERAL STUDIES OF NUCLEAR REACTORS
CARBON STEELS
FATIGUE
LOW ALLOY STEELS
STAINLESS STEELS
AUSTENITIC STEELS
PWR TYPE REACTORS
BWR TYPE REACTORS
FRACTURE MECHANICS
CRACK PROPAGATION
OXYGEN
STRAIN RATE
TEMPERATURE RANGE 0400-1000 K
RECOMMENDATIONS
CORRELATIONS
360103
220200
MECHANICAL PROPERTIES
COMPONENTS AND ACCESSORIES