Probabilistic analysis for axial cracking in Palo Verde Unit 1 steam generator tubing
Conference
·
OSTI ID:203765
- Packer Engineering Plant Component Analysis Division, Pittsburgh, PA (United States)
- Arizona Public Service, Phoenix, AZ (United States)
Axial stress corrosion cracks have been observed on the outer diameter of steam generator tubing in the upper bundle region in units at the Palo Verde Nuclear Generator Station (PVNGS). This paper describes a Monte-Carlo probabilistic model developed to provide an overall assessment of the risk of exceeding Regulatory Guide 1.121 structural limit requirements during plant operation. The chosen approach models crack initiation, crack growth, detection of cracks and subsequent removal from service. Cracking statistics from inspection results for Units 2 and 3 are used to predict the expected performance of Unit 1. A general approach to calculating the probability of structural limit exceedance as a function of run time is described for steam generator tubing experiencing stress corrosion cracking.
- OSTI ID:
- 203765
- Report Number(s):
- CONF-950816--; ISBN 1-877914-95-9
- Country of Publication:
- United States
- Language:
- English
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