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Microstructural evolution of a silicon carbide-carbon coated nanostructured ferritic alloy composite during in-situ Kr ion irradiation at 300°C 450°C

  • Kaustubh Bawane
  • , Kathy Lu
  • , Xian Ming Bai
  • , Jing Hu
  • , Meimei Li
  • , Peter M. Baldo
  • , Edward Ryan

Research output: Contribution to journalArticlepeer-review

7 Scopus citations

Abstract

This work focuses on irradiation behaviors of a novel silicon carbide and carbon coated nanostructured ferritic alloy (SiC-C@NFA) composite for potential applications as a cladding and structural material for next generation nuclear reactors. The SiC-C@NFA samples were irradiated with 1 MeV Kr ions up to 10 dpa at 300 and 450 °C. Microstructures and defect evolution were studied in-situ at the IVEM-Tandem facility at Argonne National Laboratory. The effects of ion irradiation on various phases such as α-ferrite matrix, (Fe,Cr)7C3, and (Ti,W)C precipitates were evaluated. The α-ferrite matrix showed a continuous increase in dislocation density along with spatial ordering of dislocation loops (or loop strings) at >5 dpa. The size of the dislocation loops at 450 °C was larger than that at 300 °C. The nucleation and growth of new (Ti,W)C precipitates in α-ferrite grains were enhanced with the ion dose at 450 °C. This study provides new insight into the irradiation resistance of the SiC-C@NFA system.

Original languageEnglish
Pages (from-to)75-83
Number of pages9
JournalJournal of Materials Science and Technology
Volume71
DOIs
StatePublished - Apr 30 2021
Externally publishedYes

Keywords

  • (FeCr)C
  • Ferritic steel
  • Fuel cladding
  • In-situ ion irradiation
  • Metal matrix composite

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