Dynamic crack propagation in pipes. [PWR; BWR]
This annual report contains the description of predictive models for critical flaw sizes, for initiation and propagation of dynamic cracks in pipes and the behavior of dynamic crack propagation in double cantilever beam (DCB) specimens developed during the third year of the study. Critical flaw sizes of cracks were studied by evaluating stress intensity factors under static conditions for a series of representative flaws. Fundamental properties governing rapid crack propagation and crack arrest were also studied by analyzing the fracture dynamic responses of two tapered DCB specimen. Continuing studies in the initation and propagation of axial through cracks in pressurized pipes were conducted by using an elastic-plastic finite difference shell code coupled with a one-dimensional thermal-hydraulic code which computed the leakage through the crack opening and the depressurization of the fluid in the pipe. A thermal-hydraulic code was developed to examine the axial and circumferential pressure distributions in the vicinity of the crack tip.
- Research Organization:
- Washington Univ., Seattle (USA). Dept. of Mechanical Engineering
- OSTI ID:
- 6547184
- Report Number(s):
- EPRI-NP-1742
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
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Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINERS
COOLING SYSTEMS
CRACKS
ENERGY SYSTEMS
FAILURES
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
NOZZLES
PIPES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
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WATER COOLED REACTORS
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210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINERS
COOLING SYSTEMS
CRACKS
ENERGY SYSTEMS
FAILURES
FRACTURE PROPERTIES
MECHANICAL PROPERTIES
NOZZLES
PIPES
PRESSURE VESSELS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STRESS ANALYSIS
WATER COOLED REACTORS
WATER MODERATED REACTORS