Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep
- Авторлар: Margolin B.1, Sorokin A.1, Buchatsky A.1
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Мекемелер:
- Central Research Institute of Structural Materials Prometey
- Шығарылым: Том 7, № 6 (2016)
- Беттер: 942-949
- Бөлім: Radiation Material Science
- URL: https://journals.rcsi.science/2075-1133/article/view/205889
- DOI: https://doi.org/10.1134/S2075113316060101
- ID: 205889
Дәйексөз келтіру
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.
Негізгі сөздер
Авторлар туралы
B. Margolin
Central Research Institute of Structural Materials Prometey
Хат алмасуға жауапты Автор.
Email: margolinbz@yandex.ru
Ресей, St. Petersburg, 191015
A. Sorokin
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Ресей, St. Petersburg, 191015
A. Buchatsky
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Ресей, St. Petersburg, 191015