Effect of Fuel Burnup History on Neutronic Characteristics of WWER-1000 Core
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,
 moder...
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| Published in: | Ядерна та радіаційна безпека |
|---|---|
| Date: | 2014 |
| Main Authors: | Ovdiienko, Yu.N., Yeremenko, M.L., Khalimonchuk, V.A., Kuchin, A.V., Bilodid, Yu.M. |
| Format: | Article |
| Language: | English |
| Published: |
Державне підприємство "Державний науково-технічний центр з ядерної та радіаційної безпеки" Держатомрегулювання України та НАН України
2014
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| Online Access: | https://nasplib.isofts.kiev.ua/handle/123456789/97619 |
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| Journal Title: | Digital Library of Periodicals of National Academy of Sciences of Ukraine |
| Cite this: | Effect of Fuel Burnup History on Neutronic Characteristics of WWER-1000 Core / Yu.N. Ovdiienko, M.L. Yeremenko, V.A. Khalimonchuk, A.V. Kuchin, Yu.M. Bilodid // Ядерна та радіаційна безпека. — 2014. — № 3. — С. 14-18. — Бібліогр.: 4 назв. — англ. |
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