Published August 1984
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Leak-before-break diagrams using simple plastic limit load criteria for pipes with circumferential cracks
Description
Simple criteria for local and global instabilities were used to calculate leak-before-break-diagrams for load-controlled deformations. Relations between the tension and bending stresses in the uncracked pipe and the critical crack angle α/sub c/, below which complete fracture cannot occur, were developed for combined loading by internal pressure and external tension and bending. The different assumptions made for local and global instability lead to similar conclusions about the allowable crack length for leak-before-break behavior. It was not the intention of this paper to compare the conclusions with experimental results available
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Additional details
Publishing Information
- Imprint Title
- CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings
- Journal Page Range
- p. 180-203.
- Report number
- NUREG/CP--0051
Conference
- Title
- CSNI leak-before-break conference.
- Dates
- 1-2 Sep 1983.
- Place
- Monterey, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16068221
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BENDING; CRACK PROPAGATION; CRACKS; EVALUATED DATA; FLEXURAL STRENGTH; FRACTURE PROPERTIES; FRACTURES; LEAKS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; PLASTICITY; PRIMARY COOLANT CIRCUITS; STRESSES; TENSILE PROPERTIES
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DATA; DEFORMATION; FAILURES; INFORMATION; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; THERMAL POWER PLANTS