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

A. J. Minkin; A. M. Morozov; V. I. Smirnov

doi:10.1134/S2075113318060308

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

作者: Minkin A.J.¹, Morozov A.M.¹, Smirnov V.I.¹
隶属关系:
1. National Research Center Kurchatov Institute—CRISM Prometey
期: 卷 9, 编号 6 (2018)
页面: 1237-1242
栏目: Radiation Materials Science
URL: https://journals.rcsi.science/2075-1133/article/view/207744
DOI: https://doi.org/10.1134/S2075113318060308
ID: 207744

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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.