Published April 1997 | Version v1
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Recent evaluations of crack-opening-area in circumferentially cracked pipes

Description

Leak-before-break (LBB) analyses for circumferentially cracked pipes are currently being conducted in the nuclear industry to justify elimination of pipe whip restraints and jet shields which are present because of the expected dynamic effects from pipe rupture. The application of the LBB methodology frequently requires calculation of leak rates. The leak rates depend on the crack-opening area of the through-wall crack in the pipe. In addition to LBB analyses which assume a hypothetical flaw size, there is also interest in the integrity of actual leaking cracks corresponding to current leakage detection requirements in NRC Regulatory Guide 1.45, or for assessing temporary repair of Class 2 and 3 pipes that have leaks as are being evaluated in ASME Section XI. The objectives of this study were to review, evaluate, and refine current predictive models for performing crack-opening-area analyses of circumferentially cracked pipes. The results from twenty-five full-scale pipe fracture experiments, conducted in the Degraded Piping Program, the International Piping Integrity Research Group Program, and the Short Cracks in Piping and Piping Welds Program, were used to verify the analytical models. Standard statistical analyses were performed to assess used to verify the analytical models. Standard statistical analyses were performed to assess quantitatively the accuracy of the predictive models. The evaluation also involved finite element analyses for determining the crack-opening profile often needed to perform leak-rate calculations

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Additional details

Publishing Information

Imprint Title
Proceedings of the seminar on leak before break in reactor piping and vessels
Imprint Pagination
773 p.
Journal Page Range
p. 299-314.
Report number
NUREG/CP--0155

Conference

Title
Seminar on leak before break in reactor piping and vessels.
Dates
9-11 Oct 1995.
Place
Lyon (France).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28075604
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; BENCH-SCALE EXPERIMENTS; BENDING; CALCULATION METHODS; DIMENSIONS; FLOW RATE; FRACTURE MECHANICS; LEAK DETECTORS; LEAKS; MATHEMATICAL MODELS; PIPES
Descriptors DEC
DEFORMATION; MECHANICS

Optional Information

Contract/Grant/Project number
Contract NRC-04-90-069
Secondary number(s)
CONF-9510432--.