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High-Temperature Strength of KTTs-110 Zirconium Alloy
Authors:Kovalev  V. V.  Kisilevskii  V. N.  Borisenko  V. A.  Bukhanovskii  V. V.
Affiliation:(1) Pisarenko Institute of Problems of Strength, National Academy of Sciences of Ukraine, Kiev, Ukraine
Abstract:We describe the methods and results of investigation of the characteristics of strength and plasticity of a pilot batch of tubes made of KTTs-110 zirconium alloy under the conditions of short- and long-term static loading. The obtained results are compared with the same characteristics of É-110 alloy extensively used in the active zones of WWÉR-1000-type nuclear reactors.
Keywords:nuclear reactors  zirconium alloy  short-term strength  plasticity  tangential direction  longitudinal direction  creep  creep rate
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