Abstract
Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel were studied in simulated pressurized water reactor primary water. The microstructure of the oxide formed on the steel irradiated to different doses over an exposure period range of 25–1500 h was analyzed and compared. It was found that the general and intergranular corrosion rates of the steel were increased with irradiation dose, in correspondence with an evolution of the general oxide and the oxide formed at the grain boundary. Correlation of the oxide evolution with the corrosion kinetics and mechanism has been discussed in detail.
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Acknowledgements
This work was financially supported by the International Science & Technology Cooperation Program of China (No. 2014DFA50800) and partly supported by the Essential Research Fund by SNPTC (No. 2015SN010-007). The authors gratefully acknowledge the Michigan Ion Beam Laboratory at the University of Michigan for performing proton implantation experiments.
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Deng, P., Han, EH., Peng, Q. et al. Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water. Acta Metall. Sin. (Engl. Lett.) 34, 174–186 (2021). https://doi.org/10.1007/s40195-020-01123-y
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DOI: https://doi.org/10.1007/s40195-020-01123-y