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Оцінка впливу невизначеності у вихідних даних на результати аналізу критичності ядерного палива
The paper presents parameters calculated with SCALE-4.4 code to assess impact of fabrication tolerances and uncertainty of input data on geometrical and material composition of VVER-1000 fuel assembly (FA) elements on results of nuclear fuel criticality analysis. The most conservative set of paramet...
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| Main Authors: | , |
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| 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/305 |
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