Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep
- Авторы: Margolin B.Z.1, Sorokin A.A.1, Buchatsky A.A.1
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Учреждения:
- Central Research Institute of Structural Materials Prometey
- Выпуск: Том 7, № 6 (2016)
- Страницы: 942-949
- Раздел: Radiation Material Science
- URL: https://journals.rcsi.science/2075-1133/article/view/205889
- DOI: https://doi.org/10.1134/S2075113316060101
- ID: 205889
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Аннотация
A method that allows predicting the crack growth rate in austenitic steels under neutron irradiation creep is developed. A relation for prediction of the crack growth rate in the material of the VVER reactor internals is derived and its maximum value is assessed.
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Об авторах
B. Margolin
Central Research Institute of Structural Materials Prometey
Автор, ответственный за переписку.
Email: margolinbz@yandex.ru
Россия, St. Petersburg, 191015
A. Sorokin
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Россия, St. Petersburg, 191015
A. Buchatsky
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Россия, St. Petersburg, 191015
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