<p>Probabilistic fracture mechanics (PFM) is expected as a more rational methodology for structural integrity assessments of components in nuclear power plants because it can evaluate failure probabilities of the components quantitatively and consider inherent uncertainties in the various influencing factors. The Japan Atomic Energy Agency (JAEA) has developed a PFM analysis code, PASCAL-SP, to evaluate failure probabilities of piping due to aging degradation mechanisms such as fatigue and stress-corrosion cracking in the environments of both pressurized-water and boiling-water reactors. To improve confidence in the analysis results obtained from PASCAL-SP, a benchmarking study was conducted together with the PFM analysis code, xLPR, which was developed jointly by the U.S. Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute. The benchmarking study was composed of deterministic and probabilistic analyses related to primary water stress-corrosion cracking in a dissimilar metal weld joint in a pressurized-water reactor surge line. The analyses were conducted by the NRC staff and JAEA independently using their respective codes and under common analysis conditions. In the present paper, the analysis conditions for the deterministic and probabilistic analyses are described in detail, and the analysis results obtained from the xLPR and PASCAL-SP codes are presented. It was confirmed that the analysis results obtained from the two codes are in good statistical agreement.</p>

Benchmarking Study on Probabilistic Fracture Mechanics Analysis Codes xLPR and PASCAL-SP Considering Primary Water Stress Corrosion Cracking

Paper Proceedings: https://asmedigitalcollection.asme.org/PVP/PVP2021/volume/85314

ASME 2021 Pressure Vessels & Piping Conference (PVP2021)

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