Published 1992 | Version v1
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Experimental investigation of flawed pipes with respect to fracture behavior and development of crack opening area

Creators

  • 1. Stuttgart Univ. (Germany). Staatliche Materialpruefungsanstalt

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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Part of:
Principal working group 3 on primary circuit integrity

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

Optional Information