Predicting the life of high-temperature structural components in power plants
Journal Article
·
· JOM (Journal of the Minerals, Metals and Materials Society); (United States)
- Westinghouse Science and Technology Center, Pittsburgh, PA (US)
- Georgia Inst. of Technology, Atlanta, GA (US)
- Detroit Edison Co., Detroit, MI (US)
This paper reports on the concept of time-dependent fracture mechanics that has been used to develop the quantitative life-prediction methodology and inspection criteria for high-temperature structural components. As an example, the methodology was applied to steam pipes. Leak-before-break analyses were utilized to determine the flaw inspection criteria of steam pipes. Both static and cyclic loading conditions were included in the life-prediction analyses. Increasing the frequency of shut-downs was found to decrease the remaining life. The effects of operating pressures and temperatures and material properties on the life of steam pipes were quantified.
- OSTI ID:
- 5710540
- Journal Information:
- JOM (Journal of the Minerals, Metals and Materials Society); (United States), Vol. 44:2
- Country of Publication:
- United States
- Language:
- English
Similar Records
Considerations for Probabilistic Analyses to Assess Potential Changes to Large-Break LOCA Definition for ECCS Requirements
Recent evaluations of crack-opening-area in circumferentially cracked pipes
Probabilistic approaches to life prediction of nuclear plant structural components
Conference
·
Mon Jul 01 00:00:00 EDT 2002
·
OSTI ID:5710540
+4 more
Recent evaluations of crack-opening-area in circumferentially cracked pipes
Conference
·
Tue Apr 01 00:00:00 EST 1997
·
OSTI ID:5710540
+2 more
Probabilistic approaches to life prediction of nuclear plant structural components
Conference
·
Tue Dec 31 00:00:00 EST 1996
·
OSTI ID:5710540
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
PRESSURE VESSELS
SAFETY ANALYSIS
REACTOR COMPONENTS
PERFORMANCE TESTING
THERMOMECHANICAL TREATMENTS
STEAM LINES
FRACTURE MECHANICS
IN-SERVICE INSPECTION
MATERIALS TESTING
NUCLEAR POWER PLANTS
PRESSURE EFFECTS
TEMPERATURE EFFECTS
TIME DEPENDENCE
CONTAINERS
FABRICATION
HEAT TREATMENTS
INSPECTION
MATERIALS WORKING
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
TESTING
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220504 - Nuclear Reactor Technology- Environmental Aspects- Design Basis & Hypothetical Accidents- (1992-)
220200 - Nuclear Reactor Technology- Components & Accessories
PRESSURE VESSELS
SAFETY ANALYSIS
REACTOR COMPONENTS
PERFORMANCE TESTING
THERMOMECHANICAL TREATMENTS
STEAM LINES
FRACTURE MECHANICS
IN-SERVICE INSPECTION
MATERIALS TESTING
NUCLEAR POWER PLANTS
PRESSURE EFFECTS
TEMPERATURE EFFECTS
TIME DEPENDENCE
CONTAINERS
FABRICATION
HEAT TREATMENTS
INSPECTION
MATERIALS WORKING
MECHANICS
NUCLEAR FACILITIES
POWER PLANTS
TESTING
THERMAL POWER PLANTS
220900* - Nuclear Reactor Technology- Reactor Safety
220504 - Nuclear Reactor Technology- Environmental Aspects- Design Basis & Hypothetical Accidents- (1992-)
220200 - Nuclear Reactor Technology- Components & Accessories