Email this article Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep
- Authors: Margolin B.Z.1, Sorokin A.A.1, Buchatsky A.A.1
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Affiliations:
- Central Research Institute of Structural Materials Prometey
- Issue: Vol 7, No 6 (2016)
- Pages: 942-949
- Section: 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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Abstract
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.
About the authors
B. Z. Margolin
Central Research Institute of Structural Materials Prometey
Author for correspondence.
Email: margolinbz@yandex.ru
Russian Federation, St. Petersburg, 191015
A. A. Sorokin
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Russian Federation, St. Petersburg, 191015
A. A. Buchatsky
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
Russian Federation, St. Petersburg, 191015
