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Title: On the probability of exceeding allowable leak rates through degraded steam generator tubes

Conference ·
OSTI ID:467918
;  [1];  [2]
  1. Jozef Stefan Institute, Ljubljana (Slovenia)
  2. Forschungszentrum Karlsruhe (Germany)

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.

Research Organization:
CH2M Hill, Gainesville, FL (United States); Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI ID:
467918
Report Number(s):
NUREG/CP-0154; ANL-96/14; NEA/CNRA/R-(96)1; CONF-9510423-; ON: TI97004312; TRN: 97:008384
Resource Relation:
Conference: CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants, Oak Brook, IL (United States), 30 Oct - 2 Nov 1995; Other Information: PBD: Feb 1997; Related Information: Is Part Of Proceedings of the CNRA/CSNI workshop on steam generator tube integrity in nuclear power plants; Diercks, D.R. [Argonne National Lab., IL (United States)]; PB: 621 p.
Country of Publication:
United States
Language:
English