Nuclear Materials and Energy (Dec 2019)

Effect of aluminum content on dislocation loops in model FeCrAl alloys

  • Xiong Zhou,
  • Liping Guo,
  • Yaxia Wei,
  • Hui Wang,
  • Cheng Chen,
  • Yiheng Chen,
  • Weiping Zhang,
  • Shi Liu,
  • Renduo Liu,
  • Shaobo Mo

Journal volume & issue
Vol. 21

Abstract

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Five kinds of iron-chromium-aluminum (FeCrAl) alloy samples with different contents of aluminum (Al)—Fe-12Cr, Fe-12Cr-2Al, Fe-12Cr-4Al, Fe-12Cr-6Al, and Fe-12Cr-8Al—were designed and prepared. All samples were then irradiated with 200 keV argon ions (Ar2+) to the fluence of 9.3 × 1014 ions cm−2 at 330°C. The formations of dislocation loops induced by Ar2+ irradiation in these alloys were investigated by transmission electron microscopy. Both of a/2 and a dislocation loops were generated in all samples. The sizes of both a/2 and a dislocation loops decreased and total volume number densities increased with increasing Al content of the samples. The proportion of a/2 dislocation loops decreased first and then increased with Al content, and the ratio of a/2 to a average loop size increased first and then decreased with Al content. The experiment results indicate that the increase of Al content in alloys can enhance the nucleation and inhibit the growth of dislocation loops, the interaction between a/2 and a dislocation loops is affected by the Al content in alloys as well. The difference in dislocation loops in FeCrAl alloys with different Al contents after Ar2+ irradiation can be explained by the pinning of dislocation loops by the Al atoms. Keywords: FeCrAl alloy, Dislocation loops, Radiation damage, Accident tolerant fuel cladding