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Thermomechanical Behavior and Modeling Between 350°C and 400°C of Zircaloy-4 Cladding Tubes From an Unirradiated State to High Fluence (0 to 85⋅1024 nm−2,E>1 MeV)
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper first describes the effect of neutron irradiation on the thermomechanical behavior of stress-relieved Zircaloy-4 fuel tubes that have been analyzed after exposure to five different ...
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