Email this article Improvement of the Approach to Predict the Fracture Toughness of Irradiated Anticorrosive Cladding for WWER-Type Reactors
- Authors: Minkin A.J.1, Morozov A.M.1, Smirnov V.I.1
-
Affiliations:
- National Research Center Kurchatov Institute—CRISM Prometey
- Issue: Vol 9, No 6 (2018)
- Pages: 1237-1242
- Section: Radiation Materials Science
- URL: https://journals.rcsi.science/2075-1133/article/view/207744
- DOI: https://doi.org/10.1134/S2075113318060308
- ID: 207744
Cite item
Open Access
Access granted
Subscription Access
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.
About the authors
A. J. Minkin
National Research Center Kurchatov Institute—CRISM Prometey
Author for correspondence.
Email: mail@crism.ru
Russian Federation, St. Petersburg, 191015
A. M. Morozov
National Research Center Kurchatov Institute—CRISM Prometey
Email: mail@crism.ru
Russian Federation, St. Petersburg, 191015
V. I. Smirnov
National Research Center Kurchatov Institute—CRISM Prometey
Email: mail@crism.ru
Russian Federation, St. Petersburg, 191015
