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2018•Atomic EnergyRequires access

Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation

G. V. Kulakov, Yu. V. Konovalov, A. A. Kosaurov, M. M. Peregud, Antonina V. Nikulina, V. Yu. Shishin, В. А. Овчинников, A. A. Shel’dyakov

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Key concepts: Cladding (metalworking), Zirconium alloy, Zirconium, Alloy, Materials science, Corrosion, Metallurgy, Nuclear fuel

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Behavior of Modified Zirconium-Alloy Fuel-Element Cladding Under Irradiation — Research Paper | ScholarLens