Abstract
Probabilistic failure metrics such as leak frequency and rupture frequency are commonly used to characterize piping reliability. The methodologies for calculating the failure metrics rely on a complex set of input parameters. Operating experience data and experimental data play an important role in informing the different input parameters. The paper describes results and conclusions of a coordinated research project to benchmark three different reliability models using a four-step procedure: reference case definition of relevance to advanced reactor designs, input parameter calibration, validation of results, and application of different methodologies upon completion of the calibration and validation steps. The reference case is a weld consisting of nickel-base alloy 152/52 and located within a primary pressure boundary of an advanced reactor. This alloy is a class of structural materials known to be highly resistant to stress corrosion cracking. Synergies between the different methods are noted and the importance of a multi-disciplinary approach to input parameter development is underscored. A key conclusion is that the three methods are equally suitable for estimating failure frequencies. In any specific application, a selection of the most practical or effective computational tool can be considered. The comparison of alternative models confirms and helps to gain confidence in the computed failure frequency estimates. The study was part of a coordinated research project organized by the International Atomic Energy Agency.
| Original language | English |
|---|---|
| Article number | 111990 |
| Journal | Nuclear Engineering and Design |
| Volume | 398 |
| Early online date | Oct 2 2022 |
| DOIs | |
| State | Published - Nov 2022 |
| Externally published | Yes |
Keywords
- Advanced water cooled reactor
- Alloy 600/82/182
- Alloy 690/52/152
- Factor of improvement
- Failure frequency
- Probabilistic assessment
- Reliability and integrity management
- Stress corrosion cracking
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