The surveillance of Flow Accelerated Corrosion (FAC) on secondary pipes is a major concern for every nuclear power plant operator. After the Surry accident in 1986, EDF launched a computer code development program to monitor this degradation phenomenon. A chemical corrosion model has been developed, based on laboratory test results obtained by EDF R&D since the late 70’s. This model enables to compute the wall thickness loss of pipes submitted to FAC, with respect to the thermo-hydraulic conditions, the fluid chemistry, the material chromium content, the pipe geometry and the cycles duration.
- Nuclear Engineering Division
Making FAC Calculations With BRT-CICERO™ and Updating to Version 3.0
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Trevin, S, Persoz, M, & Knook, T. "Making FAC Calculations With BRT-CICERO™ and Updating to Version 3.0." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 81-88. ASME. https://doi.org/10.1115/ICONE17-75341
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