Nuclear fuel rod cladding and methods for producing such cladding
By using tubular inner liners and outer protective layers made of silicon carbide and/or carbon fiber reinforced ceramic matrix composites, the problems of embrittlement and oxidation of zirconium-based alloy cladding under severe accidents have been solved, improving the mechanical properties and sealing performance of nuclear fuel rod cladding and reducing the risk of nuclear fuel leakage.
Patent Information
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- FRAMATOME SA
- Filing Date
- 2024-10-16
- Publication Date
- 2026-05-26
AI Technical Summary
Existing zirconium-based alloy cladding is prone to embrittlement and oxidation under severe accident conditions, leading to nuclear fuel release, and its mechanical properties are insufficient under normal conditions.
A tubular liner made of a ceramic matrix composite material reinforced with silicon carbide and/or carbon fiber is used, which, together with an outer protective layer, forms a wear-resistant nuclear fuel rod cladding.
It improves the mechanical properties and sealing performance of the cladding under normal and accident conditions, reduces the risk of cladding rupture and nuclear fuel leakage, prevents the release of fission gases, and reduces material corrosion.
Smart Images

Figure CN122095436A_ABST