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Данная работа посвящена обоснованию параметров реакторной установки РУТА-10. Задачи, которые решались в ходе исследования: 1. Изучены конструкционные решения РУТА-10, взятые за основу; 2. Проведен нейтронно-физический расчет; 3. Проведен тепловой расчет; 4. Проведены расчёты прочностного расчета; 5. Построены чертежи. Разработка реактора проходила в постадийном формате по мере уточнения полученных результатов. Проведены расчёты нейтронно-физического, теплового и прочностного расчёта. В результате были получены параметры РУ с ВВР для атомной станции мощностью до 10 МВт.

This work is devoted to the substantiation of parameters for the RUTA-10 reactor unit. The following tasks were accomplished during the research: 1. The baseline design solutions of the RUTA-10 were studied. 2. Neutronics calculations were performed. 3. Thermal-hydraulics calculations were performed. 4. Structural integrity calculations were performed. 5. Engineering drawings were created. The reactor design process was conducted in a staged format, refining the results at each step. Calculations were performed in the areas of neutronics, thermal-hydraulics, and structural strength. As a result, optimal parameters were substantiated for a water-cooled water-moderated reactor unit intended for a nuclear power plant with a capacity of up to 10 MW.