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Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions

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Acta Metallurgica Sinica (English Letters) Aims and scope

Abstract

AL-6XN stainless steels, one of the candidate structure materials for supercritical water-cooled reactor, were irradiated from 0.5 to 5 dpa using 100 keV H2 + ions at 290 and 380 °C. Microstructures were characterized by transmission electron microscopy (TEM). Dislocation loops were the dominant radiation-induced defects. All the dislocation loops had 1/3 <111> type Burgers vector. Number density and size of the loops have been measured. Nucleation and evolution of dislocation loops were also investigated. Voids were observed only in the condition of 5 dpa at 380 °C. Different evolution mechanisms of the radiation-induced dislocation loops were discussed. Effects of hydrogen and elevated temperature on the microstructural evolution were also investigated. Besides, the formed voids have a further effect on the evolution of dislocation loops.

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Acknowledgments

The financial supports from the International Science and Technology Cooperation Program of China (No. 2015DFR60370) and the National Natural Science Foundation of China (Nos. 11275140 and U1532134) are gratefully acknowledged.

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Correspondence to Li-Ping Guo.

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Zheng, ZC., Yu, YX., Zhang, WP. et al. Evolution of Dislocation Loops in AL-6XN Stainless Steels Irradiated by Hydrogen Ions. Acta Metall. Sin. (Engl. Lett.) 30, 89–96 (2017). https://doi.org/10.1007/s40195-016-0490-2

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  • DOI: https://doi.org/10.1007/s40195-016-0490-2

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