On the probability of exceeding allowable leak rates through degraded steam generator tubes
Creators
- 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
Files
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
Optional Information
- Secondary number(s)
- ANL--96/14; NEA/CNRA/R--(96)1; CONF-9510423--.