Experimental investigation of flawed pipes with respect to fracture behavior and development of crack opening area
Description
The critical length of a longitudinal through-wall flaw, defined as that causing rupture, was first determined hydro-statically on large experimental vessels under internal pressure; the leak before rupture diagram for the base material of the vessel is established by experiment and calculation; it gives a limit between the two modes of failure, leakage or rupture (catastrophic failure), depending on slit length and loading conditions. Tests under pneumatic pressure were then carried out to investigate crack arrest, with notched discs made of a brittle material welded in the cylindrical part of the vessel, and cracks triggered by means of a small charged ignited over the notch. In the case of discs of a diameter smaller than the critical slit length, crack arrest occurred when the crack entered the tough material, while a disc corresponding to the critical crack length of the vessel led to rupture. 5 refs., 16 figs., 2 tabs
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Additional details
Publishing Information
- Imprint Title
- Principal working group 3 on primary circuit integrity
- Imprint Pagination
- 189 p.
- Journal Page Range
- p. 117-128.
- Report number
- NEA-CSNI-R--95-6
Conference
- Title
- Workshop on Reactor Coolant System Leakage and Failure Probabilities.
- Dates
- 9-11 Dec 1992.
- Place
- Cologne (Germany).
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 28008606
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CRACK PROPAGATION; CRACKS; FAILURE MODE ANALYSIS; FRACTURE MECHANICS; MECHANICAL TESTS; PRESSURE VESSELS; REACTOR COOLING SYSTEMS; RUPTURES
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; FAILURES; MATERIALS TESTING; MECHANICS; REACTOR COMPONENTS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; TESTING