Вплив урахування історії вигоряння палива на розрахункові НФХ ВВЕР-1000
In preparation of few-group cross-section libraries to be used in WWER macro-calculations, change in the nuclide composition during fuel burnup is commonly defined under invariable characteristics, averaged over the entire core (power, fuel and moderator temperature, moderator density etc.). In real...
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| Datum: | 2014 |
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| Hauptverfasser: | , , , , |
| Format: | Artikel |
| Sprache: | English |
| Veröffentlicht: |
State Scientific and Technical Center for Nuclear and Radiation Safety
2014
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| Online Zugang: | https://nuclear-journal.com/index.php/journal/article/view/400 |
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| Назва журналу: | Nuclear and Radiation Safety |