ÐÑÐ¾ÐµÐºÑ ÐÐС моÑноÑÑÑÑ 1000 ÐÐÑ Ñ ÑеакÑоÑом ÐÐ ÐСТ-1000
2022In this paper, we consider the design of a nuclear power plant with a BREST reactor with an electric power of 1000 MW. In the course of the work, thermal-hydraulic, neutron-physical calculations of the reactor were carried out. Power electrical equipment of the NPP was calculated and selected.
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ÐÑÐ¾ÐµÐºÑ ÐÐС моÑноÑÑÑÑ 1500 ÐÐÑ Ñ ÑеакÑоÑами ÐÐ-500
The purpose of this work is to develop a nuclear power plant project with a VK â 500 reactor plant installed in the Khabarovsk Territory, near the village of Mayak. The fuel assembly 2 was chosen as the fuel assembly. The initial fuel enrichment of the VK â 500 fuel assembly was changed to 3.2%. For thermal calculation, a detailed thermal scheme ofopenaire +1 more source
ÐÑÐ¾ÐµÐºÑ ÐСТ моÑноÑÑÑÑ 1000 ÐÐÑ Ñ ÑеакÑоÑами ÐСТ-500
2023The work consists in the development of the AST project in the Republic of Sakha with a AST-500 reactor facility. FA from the AST-500. The neutron-physical calculation has been performed in the four-group approximation method and in the SAPFIR_95 program. AST-500 cycle has been developed and calculated.
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ÐÑÐ¾ÐµÐºÑ ÐÐС моÑноÑÑÑÑ 1600 ÐÐÑ Ñ ÑеакÑоÑами ÐÐ-800
The work includes the choosing of the construction site, the layout of the selected main and auxiliary equipment based on the thermal calculation. Geometric, neutron-physical and thermal-hydraulic calculations of the active and lateral zones of the reactor were performed. The design of the power output circuit and the choice of electrical equipment areopenaire +1 more source
ÐÑÐ¾ÐµÐºÑ ÑеакÑоÑа Ð´Ð»Ñ Ð°Ñомного ледокола Ð ÐТР200
2019ÐÑполнено пÑоекÑиÑование аÑомного ледокола моÑноÑÑÑÑ 175 ÐÐÑ Ñ ÑеакÑоÑом Ð ÐТР200. ÐÑоизведен вÑÐ±Ð¾Ñ Ð¾Ñновного и вÑпомогаÑелÑного обоÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑнеÑгоблока. ÐÑоведен геомеÑÑиÑеÑкий, ÑеплогидÑавл
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ÐÑÐ¾ÐµÐºÑ Ð¿Ð»Ð°Ð²ÑÑего комплекÑа Ñ ÑеакÑоÑами «РÐТÐ-400»
2023In this diploma project FNPP with RITM-400 reactors paired with TK-35/38-3.4 turbines is designed. The feature of this project is turbine calculation in thermal and maximum electric power modes. Neutron-physical calculation is made in thefour-group approximation method.
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ÐÑÐ¾ÐµÐºÑ ÐÐС моÑноÑÑÑÑ 3000 ÐÐÑ Ñ ÑеакÑоÑами ÐÐÐÐ -1500
2019ÐÑполнено пÑоекÑиÑование аÑомной ÑлекÑÑоÑÑанÑии моÑноÑÑÑÑ 3000 ÐÐÑ Ñ ÑеакÑоÑами Ñипа ÐÐÐÐ -1500. ÐÑоизведен вÑÐ±Ð¾Ñ Ð¾Ñновного и вÑпомогаÑелÑного обоÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑнеÑгоблока.
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ÐÑÐ¾ÐµÐºÑ ÐÐС моÑноÑÑÑÑ 2400 ÐÐÑ Ñ ÑеакÑоÑами ÐÐÐÐ -800
2019РпоÑÑниÑелÑной запиÑке пÑедÑÑÐ°Ð²Ð»ÐµÐ½Ñ ÑезÑлÑÑаÑÑ Ð¿ÑоекÑной ÑабоÑÑ Ð½Ð°Ð´ ÐÐС моÑноÑÑÑÑ 2400 ÐÐÑ Ñ ÑÑÐµÐ¼Ñ ÑеакÑоÑами Ñипа ÐÐÐÐ -800. ÐÑоизведен вÑÐ±Ð¾Ñ Ð¾Ñновного и вÑпомогаÑелÑного обоÑÑÐ´Ð¾Ð²Ð°Ð½Ð¸Ñ ÑнеÑгобР...
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Модульный реактор малой мощности с естественной циркуляцией “модест”
Ядерная физика и инжиниринг, 2020Ю. Н. Волков +1 more
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