Abstract
Alloy 800 nuclear grade (NG) is a material of choice for replacement steam generators (SG) due to its inherent resistance to primary water stress corrosion cracking (SCC). However, the long term performance of SGs depends on the performance of the material in upset conditions. Various degradation modes have been observed in Alloy 800NG under simulated secondary crevice environments (SCE) in C-ring and CERT experiments. Furthermore, the first incidences of SCE SCC have been observed in Alloy 800NG SG tubes in nuclear power plants and may be the sentinel events at the onset of more extensive cracking in the future. Understanding the parametric dependencies of SCC obtained under representative SCE and plausible transient conditions are keys to predicting future SG performance, validating mitigation strategies, and addressing life extension issues. The results of SCE crack growth rate (CGR) testing of Alloy 800NG in conditions representative of an acid-sulfate chemistry upset condition will be presented.
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Acknowledgements
The authors gratefully acknowledge Peter Andresen of GE R&D for his expert advice on CGR testing, and Sandy MacKay of Ontario Power Generation for performing the MULTEQ calculations of the standard and modified crevice chemistry pH.
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Komar, ML., Goszczynski, G. (2019). Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment. In: Jackson, J., Paraventi, D., Wright, M. (eds) Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors. The Minerals, Metals & Materials Series. Springer, Cham. https://doi.org/10.1007/978-3-030-04639-2_162
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