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nuclear fuel cladding
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Current data, viewed at
Yearly
resolution.
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Application
keyword
nuclear fuel cladding
RIS
0.002
(Research Intensity Score)
Papers
437
Top papers
An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures
2024 · 48 citations
Diffusion bonding, brazing and resistance welding of zirconium alloys: a review
2023 · 50 citations
Mechanisms of Al2O3 and Cr2O3 formation during FeCrAl alloy Oxidation: A First-Principles study
2023 · 31 citations
Enhancing the oxidation behaviors of Zr alloys for nuclear fuel cladding using nanolamellar Cr/CrN coating
2023 · 30 citations
Exploring the hydride-slip interaction in zirconium alloys
2023 · 32 citations
Newest papers
Processing maps and microstructural characterization of typical regions during hot deformation of N36 zirconium alloy
2026 · 2 citations
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
Effect of Micro‐Alloying Elements on the Interfacial Behavior and Properties of Diffusion‐Bonded Zirconium Alloys
2026
Experimental setup development and preliminary results on radioactive noble gas transport in liquid lead using the gas-jet facility at PSI
2026
Enhancing the reliability of Zr-3/SiC heterostructures via laser surface modification: Interfacial reaction control, residual stress relief and mechanical interlocking
2026
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