Some research in the field of leak before break criteria for piping
Creators
Description
Leak-before-break research activity has lead to the following basic results: a) From an extensive analysis of the available experimental data it is concluded that the concept of net section collapse is a simple, reliable, valid tool in the case of very ductile materials. b) The analysis of some experimental data has lead to the conclusion that for partially ductile materials mixed ductile, fragile conditions may be present. c) From the analyses at a and b criteria have been established in order to compute collapse conditions for through cracked pipes as a function of the applied load (moment and axial load) in terms of net section collapse. d) The role of the thermal and secondary self equilibrating loads is discussed. e) The leak areas are often evaluated on the basis of the 0.1 Aflow criterion, i.e. somewhat arbitrarily assuming a leak area equal to 10% the pipe flow area. f) The 0.1 Aflow criteria is applied to typical lines, and it is concluded that such loads can be taken without using the classical pipe whip restraints, even if some increase in the size of the snubbers might be necessary
Files
Additional details
Publishing Information
- Imprint Title
- CSNI specialist meeting on leak-before-break in nuclear reactor piping: proceedings
- Journal Page Range
- p. 386-403.
- 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
- 16068223
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CRACK PROPAGATION; CRACKS; DUCTILITY; FLOW STRESS; FRACTURE MECHANICS; FRACTURES; ITALY; LEAKS; LOSS OF COOLANT; NUCLEAR POWER PLANTS; PIPES; PRIMARY COOLANT CIRCUITS; STRESS ANALYSIS; TEARING INSTABILITY
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DEVELOPED COUNTRIES; EUROPE; FAILURES; INSTABILITY; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; PLASMA INSTABILITY; PLASMA MACROINSTABILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; STRESSES; TENSILE PROPERTIES; THERMAL POWER PLANTS