Neutron irradiation effects in Fe and Fe-Cr at 300 °c

Wei Ying Chen, Yinbin Miao, Jian Gan, Maria A. Okuniewski, Stuart A. Maloy, James F. Stubbins

Research output: Contribution to journalArticlepeer-review


Fe and Fe-Cr (Cr = 10-16 at.%) specimens were neutron-irradiated at 300 °C to 0.01, 0.1 and 1 dpa. The TEM observations indicated that the Cr significantly reduced the mobility of dislocation loops and suppressed vacancy clustering, leading to distinct damage microstructures between Fe and Fe-Cr. Irradiation-induced dislocation loops in Fe were heterogeneously observed in the vicinity of grown-in dislocations, whereas the loop distribution observed in Fe-Cr is much more uniform. Voids were observed in the irradiated Fe samples, but not in irradiated Fe-Cr samples. Increasing Cr content in Fe-Cr results in a higher density, and a smaller size of irradiation-induced dislocation loops. Orowan mechanism was used to correlate the observed microstructure and hardening, which showed that the hardening in Fe-Cr can be attributed to the formation of dislocation loops and α′ precipitates.

Original languageEnglish (US)
Pages (from-to)407-416
Number of pages10
JournalActa Materialia
StatePublished - Jun 1 2016


  • Dislocation loop
  • Fe-Cr
  • Hardness
  • Irradiation
  • Neutron
  • Orowan
  • Void

ASJC Scopus subject areas

  • Electronic, Optical and Magnetic Materials
  • Ceramics and Composites
  • Polymers and Plastics
  • Metals and Alloys


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