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nuclear fuel cladding
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resolution.
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Application
keyword
nuclear fuel cladding
RIS
0.001
(Research Intensity Score)
Papers
122
Top papers
An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures
2024 · 39 citations
Diffusion bonding, brazing and resistance welding of zirconium alloys: a review
2023 · 48 citations
Exploring the hydride-slip interaction in zirconium alloys
2023 · 30 citations
Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C
2025 · 8 citations
Enhanced accident tolerance properties of AlCrCuFeMoNbx high entropy coating for nuclear fuel cladding
2024 · 12 citations
Structural and chemical insights on the incorporation of americium into zircaloy-derived monoclinic zirconia
2025 · 4 citations
Investigation of the temperature-dependent failure processes in PVD Cr-coated ZIRLO nuclear fuel cladding using in situ X-ray micro-tomography imaging
2025 · 6 citations
Evaluation of the nuclear and mechanical properties of zirconia-reinforced aluminum alloy as nuclear fuel cladding in nuclear research reactors
2026
Processing maps and microstructural characterization of typical regions during hot deformation of N36 zirconium alloy
2026 · 2 citations
Newest papers
Evaluation of the nuclear and mechanical properties of zirconia-reinforced aluminum alloy as nuclear fuel cladding in nuclear research reactors
2026
Processing maps and microstructural characterization of typical regions during hot deformation of N36 zirconium alloy
2026 · 2 citations
Towards Zirconium Metal Production from Zircon Concentrate and Zirconia Powder Using Hydrogen Plasma Smelting Reduction
2026
Probabilistic failure assessment of spent nuclear fuel cladding based on critical crack depth
2026
The influence of Zr in the AlCrMoNbZr high-entropy alloy on the mechanical strength and corrosion resistance as a nuclear fuel cladding material
2026 · 1 citations
Oxidation of zirconium alloys for nuclear fuel cladding
2026
Improved High-Temperature Oxidation Resistance of Zirconium Alloy via a Cr Coating on a ZrO 2 Interlayer Deposited by Multi-Arc Ion Plating
2026
High Temperature High Vacuum Mechanical Property Assessment of Zirconium Nuclear Fuel Cladding
2026
Thermal creep in Zircaloy-4 nuclear fuel cladding alloy
2026
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