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 language | English |
|---|---|
| Pages (from-to) | 75-83 |
| Number of pages | 9 |
| Journal | Journal of Materials Science and Technology |
| Volume | 71 |
| DOIs | |
| State | Published - Apr 30 2021 |
| Externally published | Yes |
Keywords
- (FeCr)C
- Ferritic steel
- Fuel cladding
- In-situ ion irradiation
- Metal matrix composite
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