Кореляційний підхід до оцінки критичної температури крихкості матеріалів корпусів реакторів ВВЕР-1000 у неопроміненому стані
A statistical data analysis for ten WWER-1000 units of Ukrainian nuclear power plants has been performed to derive the relationship between the critical brittleness temperatures Тk0 (technical data on reactor pressure vessel) and Тkt (surveillance test data) for base and weld metal in unirradiated c...
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| Date: | 2015 |
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| Main Author: | |
| Format: | Article |
| Language: | Ukrainian |
| Published: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2015
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| Online Access: | https://nuclear-journal.com/index.php/journal/article/view/348 |
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| Journal Title: | Nuclear and Radiation Safety |