Fatigue strength of ASME SA 106-B welded steel pipes in 288/degree/C air environments
Technical Report
·
OSTI ID:6798340
Fatigue life tests were performed on 102-mm (4-in.) girth butt welded SA 106-B steel pipes in 288/degree/C air under axial loading with a load ratio (R) of -1.00. The fatigue strength at 10X cycles was determined to have an extrapolated value of 66.9 MPa (9.7 ksi), and the fatigue strength reduction factor (K/sub f/) was determined to be 3.47. Crack initiation usually occurred at the notch located at the internal weld fusion line on the inside diameter of each pipe, at the point of weld bead overlay. In all cases, the fatigue crack progressed on a plane normal to the pipe axis. The presence and relative number of secondary initiation sites, observed at internal weld fusion line locations around the pipe circumference, appeared to be a function of applied stress amplitude. ASME Section III analysis of the data, using the procedures given in NB-3228.5 and NB-3653.5, resulted in alternating stress (S/sub alt/) values which were conservative when compared to the ASME Section III mean data line for carbon steels. The results of this study successfully provide baseline data for comparison with proposed fatigue life tests of girth butt welded pipes containing 288/degree/C PWR environments at 13.8 MPa, under axial loading at a cyclic frequency of 0.017 Hz. 25 refs., 18 figs., 5 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Engineering; Materials Engineering Associates, Inc., Lanham, MD (USA)
- OSTI ID:
- 6798340
- Report Number(s):
- NUREG/CR-5195; ON: TI89005362
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fatigue life characterization of smooth and notched piping steel specimens in 288/degree/C air environments
Fatigue strength of smooth and notched specimens of ASME SA 106-B steel in PWR (pressurized water reactor) environments
Effect of cyclic frequency on the fatigue life of ASME SA-106-B piping steel in PWR environments
Technical Report
·
Sun May 01 00:00:00 EDT 1988
·
OSTI ID:5012821
Fatigue strength of smooth and notched specimens of ASME SA 106-B steel in PWR (pressurized water reactor) environments
Technical Report
·
Thu Sep 01 00:00:00 EDT 1988
·
OSTI ID:6815165
Effect of cyclic frequency on the fatigue life of ASME SA-106-B piping steel in PWR environments
Journal Article
·
Thu Dec 31 23:00:00 EST 1987
· Journal of Materials Engineering; (USA)
·
OSTI ID:5161434
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
BWR TYPE REACTORS
CRACKS
DATA
DATA ANALYSIS
EVALUATION
EXPERIMENTAL DATA
FATIGUE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
NUMERICAL DATA
PIPES
PWR TYPE REACTORS
REACTORS
STEELS
TESTING
THERMAL FATIGUE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ALLOYS
BWR TYPE REACTORS
CRACKS
DATA
DATA ANALYSIS
EVALUATION
EXPERIMENTAL DATA
FATIGUE
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MECHANICAL PROPERTIES
NUMERICAL DATA
PIPES
PWR TYPE REACTORS
REACTORS
STEELS
TESTING
THERMAL FATIGUE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS