Publication: Segregation of Alloying Elements on Small-Angle Grain Boundaries in Ferritic-Martensitic Steels under Ion Irradiation
Дата
2020
Авторы
Iskandarov, N. A.
Nikitin, A. A.
Khomich, A. A.
Khoroshilov, V. V.
Rogozhkin, S. V.
Potekhin, A. A.
Zaluzhnyi, A. G.
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© 2020, Pleiades Publishing, Ltd.Abstract: Segregation of chemical elements was studied in ferritic-martensitic steels RUSFER-EK-181 and ChS-139—promising structural materials for fast neutron reactor core. To simulate the radiation effects, Fe ions with an energy of 5.6 MeV at temperatures of 250–400°C to damage doses of ~6 dpa and at temperatures of 350–450°C to a damage dose of 30 dpa were used. RUSFER-EK-181 steel was also studied after thermal aging at 450°C for 5000 h. Z-contrast analysis of the irradiated steels revealed the segregation of alloying elements on dislocations at small-angle tilt and mixed grain boundaries. Atom probe tomography of the ion-irradiated ChS-139 steel showed that clusters enriched in Ni, Si, and Mn were formed on the dislocations, including dislocations of small-angle grain boundaries. Clusters enriched in Si were formed on dislocations in the RUSFER-EK-181 steel. In the aged state of RUSFER-EK-181 steel, segregation of Cr, V, Mn, Si, and N was shown at dislocations of the small-angle grain boundary. The calculated misorientation angles of the small-angle grain boundaries were ~1°–3°, and the twist angle of the mixed boundary was ~3°.
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Segregation of Alloying Elements on Small-Angle Grain Boundaries in Ferritic-Martensitic Steels under Ion Irradiation / Iskandarov, N.A. [et al.] // Inorganic Materials: Applied Research. - 2020. - 11. - № 5. - P. 1103-1109. - 10.1134/S2075113320050275