Exceptional irradiation and corrosion resistances of a TaC nanoceramic coating deposited onto ZIRLO™ fuel cladding

Abstract Improving the accident tolerance of zirconium-based nuclear fuel claddings is essential to mitigate oxidation-driven hydrogen generation under loss-of-coolant conditions. Here, a nanostructured tantalum carbide (TaC) ceramic coating is deposited onto ZIRLO™ fuel cladding by non-reactive DC magnetron sputtering. The coating was systematically assessed with respect to its microstructural stability, irradiation tolerance, and corrosion behaviour. Characterisation of as-deposited coating confirms a dense, nanocrystalline B1-type TaC structure with excellent adhesion and negligible interdiffusion at the coating-substrate interface. In situ transmission electron microscopy with heavy-ion irradiation up to ~8 dpa reveals exceptional radiation resistance, with no evidence of amorphization, phase decomposition, or radiation-induced segregation. Limited grain coarsening and the formation of Xe bubbles (~2 nm) were observed. Electrochemical measurements in borated aqueous media demonstrated rapid passivation, very low corrosion current densities, and high impedance over prolonged exposure. These results identify nanostructured TaC as a robust and scalable candidate coating for accident-tolerant fuel cladding systems.

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Publication Details

Journal
npj Materials Degradation
Published
2026-05-29
DOI
https://doi.org/10.1038/s41529-026-00813-9
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.00

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article

Exceptional irradiation and corrosion resistances of a TaC nanoceramic coating deposited onto ZIRLO™ fuel cladding

Graeme Greaves, Barbara Osinger, Vladimir Vishnyakov, Per Eklund et al.
npj Materials Degradation
Nuclear Materials and Properties
article

Exceptional irradiation and corrosion resistances of a TaC nanoceramic coating deposited onto ZIRLO™ fuel cladding

Graeme Greaves, Barbara Osinger, Vladimir Vishnyakov, Per Eklund, Stefan Fritze, Petter Ström, Oscar M. Prada-Ramirez, Matheus A. Tunes
article en

Abstract

Abstract Improving the accident tolerance of zirconium-based nuclear fuel claddings is essential to mitigate oxidation-driven hydrogen generation under loss-of-coolant conditions. Here, a nanostructured tantalum carbide (TaC) ceramic coating is deposited onto ZIRLO™ fuel cladding by non-reactive DC magnetron sputtering. The coating was systematically assessed with respect to its microstructural stability, irradiation tolerance, and corrosion behaviour. Characterisation of as-deposited coating confirms a dense, nanocrystalline B1-type TaC structure with excellent adhesion and negligible interdiffusion at the coating-substrate interface. In situ transmission electron microscopy with heavy-ion irradiation up to ~8 dpa reveals exceptional radiation resistance, with no evidence of amorphization, phase decomposition, or radiation-induced segregation. Limited grain coarsening and the formation of Xe bubbles (~2 nm) were observed. Electrochemical measurements in borated aqueous media demonstrated rapid passivation, very low corrosion current densities, and high impedance over prolonged exposure. These results identify nanostructured TaC as a robust and scalable candidate coating for accident-tolerant fuel cladding systems.

npj Materials Degradation
Uppsala University (SE), University of Huddersfield (GB), Universidade de São Paulo (BR), Montanuniversität Leoben (AT), United Kingdom Atomic Energy Authority (GB)
Stiftelsen för Strategisk Forskning, Knut och Alice Wallenbergs Stiftelse, Vetenskapsrådet, Österreichische Forschungsförderungsgesellschaft, Engineering and Physical Sciences Research Council
Openalex Percentile: Top 12%
Nuclear Materials and Properties
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