Published February 1997 | Version v1
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On the probability of exceeding allowable leak rates through degraded steam generator tubes

  • 1. Jozef Stefan Institute, Ljubljana (Slovenia)
  • 2. Forschungszentrum Karlsruhe (Germany)

Description

This paper discusses some possible ways of predicting the behavior of the total leak rate through the damaged steam generator tubes. This failure mode is of special concern in cases where most through-wall defects may remain In operation. A particular example is the application of alternate (bobbin coil voltage) plugging criterion to Outside Diameter Stress Corrosion Cracking at the tube support plate intersections. It is the authors aim to discuss some possible modeling options that could be applied to solve the problem formulated as: Estimate the probability that the sum of all individual leak rates through degraded tubes exceeds the predefined acceptable value. The probabilistic approach is of course aiming at reliable and computationaly bearable estimate of the failure probability. A closed form solution is given for a special case of exponentially distributed individual leak rates. Also, some possibilities for the use of computationaly efficient First and Second Order Reliability Methods (FORM and SORM) are discussed. The first numerical example compares the results of approximate methods with closed form results. SORM in particular shows acceptable agreement. The second numerical example considers a realistic case of NPP in Krsko, Slovenia

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Additional details

Publishing Information

Imprint Title
Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants
Imprint Pagination
621 p.
Journal Page Range
p. 533-542.
Report number
NUREG/CP--0154

Conference

Title
CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants.
Dates
30 Oct - 2 Nov 1995.
Place
Oak Brook, IL (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28068507
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
DEFECTS; FAILURE MODE ANALYSIS; KRSKO REACTOR; LEAKS; PROBABILISTIC ESTIMATION; STEAM GENERATORS; TUBES
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

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