Improvement of the Approach to Predict the Fracture Toughness of Irradiated Anticorrosive Cladding for WWER-Type Reactors

Аннотация

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.