电邮这篇文章 Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep
- 作者: Margolin B.1, Sorokin A.1, Buchatsky A.1
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隶属关系:
- Central Research Institute of Structural Materials Prometey
- 期: 卷 7, 编号 6 (2016)
- 页面: 942-949
- 栏目: 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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详细
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.
作者简介
B. Margolin
Central Research Institute of Structural Materials Prometey
编辑信件的主要联系方式.
Email: margolinbz@yandex.ru
俄罗斯联邦, St. Petersburg, 191015
A. Sorokin
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
俄罗斯联邦, St. Petersburg, 191015
A. Buchatsky
Central Research Institute of Structural Materials Prometey
Email: margolinbz@yandex.ru
俄罗斯联邦, St. Petersburg, 191015
