Parametric calculations of fatigue-crack growth in piping. [PWR; BWR]
A major objective of this program is to provide data that can be used to formulate recommended revisions to ASME Section XI and regulatory requirements for inservice inspection of piping and pressure vessels. This study presents calculations of the growth of piping flaws produced by fatigue. Flaw growth was predicted as a function of the initial flaw size, the level and number of stress cycles, the piping material, and environmental factors.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- DOE Contract Number:
- AC06-76RL01830
- OSTI ID:
- 6214697
- Report Number(s):
- NUREG/CR-3059; PNL-4537; ON: DE83009263
- Country of Publication:
- United States
- Language:
- English
Similar Records
Parametric calculations of fatigue-crack growth in piping. [PWR; BWR]
Crack Growth Evaluation for Small Cracks in Reactor Coolant Piping
Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report: October 1991--March 1992
Conference
·
Wed Jun 01 00:00:00 EDT 1983
·
OSTI ID:5874523
Crack Growth Evaluation for Small Cracks in Reactor Coolant Piping
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Thu Mar 31 23:00:00 EST 1983
·
OSTI ID:1086280
Nondestructive Examination (NDE) Reliability for Inservice Inspection of Light Water Reactors. Volume 15, Semiannual report: October 1991--March 1992
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Wed Sep 01 00:00:00 EDT 1993
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210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
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Light-Water Moderated
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36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
ALLOYS
BWR TYPE REACTORS
CRACKS
DEFECTS
FATIGUE
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
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PIPES
PWR TYPE REACTORS
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STEELS
STRESS ANALYSIS
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS