首页|Effect of yttrium content on microstructure and irradiation behavior of V-4Cr-4Ti-xY alloys
Effect of yttrium content on microstructure and irradiation behavior of V-4Cr-4Ti-xY alloys
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NSTL
Elsevier
V-4Cr-4Ti-xY alloys with different yttrium (Y) contents (x = 0, 0.1, 1 wt. %) were prepared and irradiated with Fe2+ at 550 degrees C to the peak damage dose of 35 dpa (displacement per atom). The microstructure and hardness of the alloys before and after irradiation were obtained with transmission electron microscopy (TEM), scanning electron microscopy (SEM) and nano-indentation test. With the increase of Y contents, the grain size decreased monotonously, and the formation of needle-like Ti-rich precipitates was sup -pressed. After irradiation, voids were not observed in Y added alloys but in the V-4Cr-4Ti alloy, showing that the addition of Y could inhibit the formation of voids and irradiation-induced swelling. Dislocation loops and obvious irradiation hardening were observed in all V-4Cr-4Ti-xY alloys, and the size of the dis-location loops and the irradiation hardness increment decreased with the increase of the Y content. The irradiation-induced growth of Ti-rich precipitates was observed, which may be an important factor con-tributing to the irradiation hardening besides the dislocation loops and voids. The possible mechanism of the effect of the Y element on the irradiation behavior was discussed. Among the three Y contents, V-4Cr-4Ti-1Y alloy exhibits the best performance in the suppression of the formation of Ti-rich precipitates and irradiation hardening. (C) 2021 Elsevier B.V. All rights reserved.
NSTL
Elsevier
