Abstract
Abstract—The paper presents the results of experimental investigations on the fracture toughness of anticorrosive cladding for the reactor pressure vessel of WWER-type reactors after irradiation in a range from 0 to 1.8 × 1020 neutron/cm2. On the basis of these data and results obtained earlier, the fracture toughness is derived by statistical analysis methods as a function of neutron fluence and test temperature.
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