Программные средства, применяемые для анализа и обоснования безопасности атомной электростанции в части нейтронно-физических вычислений
DOI:
https://doi.org/10.33408/2519-237X.2017.1-3.361Ключевые слова:
атомные электростанции, анализ безопасности, обоснование безопасности, ядерный реактор, активная зона, нейтронно-физические расчеты, программные средства, безопасность атомных электростанцийАннотация
Представлен обзор нейтронно-физических программных средств различных стран, используемых для анализа и обоснования безопасности блока АЭС, в том числе для определения параметров активной зоны блока АЭС в различных режимах эксплуатации, расчета топливной кампании, выгорания ядерного топлива и т. д. Рассмотрены программные средства для создания библиотек малогрупповых констант, включающих нейтронные макроскопические сечения элементов активных зон ядерных реакторов в зависимости от физических характеристик ядерного реактора, программы-имитаторы активных зон ядерных реакторов для сравнительно быстрых вычислений нейтронно-физических характеристик на основе предварительно подготовленной библиотеки малогрупповых констант, и прецизионные программы на основе метода Монте-Карло. Предложены программные средства для проведения нейтронно-физических расчетов ядерных реакторов Белорусской АЭС эксплуатирующей организацией и регулирующим органом и его организациями технической поддержки.
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