Enviar artigo por via de e-mail Improvement of the Approach to Predict the Fracture Toughness of Irradiated Anticorrosive Cladding for WWER-Type Reactors
- Autores: Minkin A.1, Morozov A.1, Smirnov V.1
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Afiliações:
- National Research Center Kurchatov Institute—CRISM Prometey
- Edição: Volume 9, Nº 6 (2018)
- Páginas: 1237-1242
- Seção: 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.
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Sobre autores
A. Minkin
National Research Center Kurchatov Institute—CRISM Prometey
Autor responsável pela correspondência
Email: mail@crism.ru
Rússia, St. Petersburg, 191015
A. Morozov
National Research Center Kurchatov Institute—CRISM Prometey
Email: mail@crism.ru
Rússia, St. Petersburg, 191015
V. Smirnov
National Research Center Kurchatov Institute—CRISM Prometey
Email: mail@crism.ru
Rússia, St. Petersburg, 191015
