J. Mater. Sci. Technol. ›› 2021, Vol. 71: 75-83.DOI: 10.1016/j.jmst.2020.07.025

• Research Article • Previous Articles     Next Articles

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

Kaustubh Bawanea, Kathy Lua,*(), Xian-Ming Baia, Jing Hub, Meimei Lib, Peter M. Baldob, Edward Ryanb   

  1. a Department of Materials Science and Engineering, Virginia Tech, Blacksburg, VA, USA
    b IVEM-Tandem Facility, Argonne National Laboratory, Lemont, IL, USA
  • Received:2020-04-30 Revised:2020-07-11 Accepted:2020-07-12 Published:2021-04-30 Online:2021-04-30
  • Contact: Kathy Lu
  • About author:* E-mail address: klu@vt.edu (K. Lu).

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.

Key words: In-situ ion irradiation, Ferritic steel, (FeCr)7C3, Metal matrix composite, Fuel cladding