Research of impact of kind resuperheat and structure of system regenerative feed water to thermodynamic efficiency of cycle with steamcoolant reactor / S. Maykova [et al.]

Уровень набора: (RuTPU)RU\TPU\network\4526, MATEC Web of ConferencesАльтернативный автор-лицо: Maykova, S., Svetlana;Borisov, V., Vassily;Antonova, A. M., specialist in the field of power engineering, Associate Professor of Tomsk Polytechnic University, Candidate of technical sciences, 1952-, Aleksandra Mikhailovna;Vorobiev, A. V., specialist in the field of power engineering, Associate Professor of Tomsk Polytechnic University, Candidate of technical sciences, 1949-, Aleksandr Vladimirovich;Abramovskikh, A. A., specialist in the field of power engineering, senior lecturer of Tomsk Polytechnic University, 1982-, Aleksey AndreevichКоллективный автор (вторичный): Национальный исследовательский Томский политехнический университет (ТПУ), Инженерная школа энергетики (ИШЭ), Научно-образовательный центр И. Н. Бутакова (НОЦ И. Н. Бутакова);Национальный исследовательский Томский политехнический университет (ТПУ), Энергетический институт (ЭНИН), Кафедра атомных и тепловых электростанций (АТЭС)Язык: английский.Резюме или реферат: The first key problems of modern nuclear reactors are inability of closed nuclear cycle, problems with spent nuclear fuel, poor effectiveness of nuclear fuel and heat-exchange equipment usage. Dealing with problems consists in usage of fast-neutron reactors with steam coolant. Scientific men analyzed neutron-physical processes in steamcooled fast reactor and consulted that creation of the reactor is viable. In consequence of low steam activation a single-loop steam cycle may be create. The cycle is easy and fool-proof. Core thermomechanical equipment has mastered and has relatively low metal content. Results of calculation are showing that nuclear unit with steam-coolant fast neutron reactor is more efficient than widely used unit with reactor VVER. Usage of simple scheme with four regenerative feedwater heaters the absolute efficiency ratio is more than 43%..Примечания о наличии в документе библиографии/указателя: [References: 7 tit.].Тематика: электронный ресурс | труды учёных ТПУ | рекуперация | тепло | питательная вода | термодинамическая эффективность | ядерные реакторы | ядерное топливо | отработанное топливо | теплообменное оборудование | реакторы на быстрых нейтронах Ресурсы он-лайн:Щелкните здесь для доступа в онлайн | Щелкните здесь для доступа в онлайн
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[References: 7 tit.]

The first key problems of modern nuclear reactors are inability of closed nuclear cycle, problems with spent nuclear fuel, poor effectiveness of nuclear fuel and heat-exchange equipment usage. Dealing with problems consists in usage of fast-neutron reactors with steam coolant. Scientific men analyzed neutron-physical processes in steamcooled fast reactor and consulted that creation of the reactor is viable. In consequence of low steam activation a single-loop steam cycle may be create. The cycle is easy and fool-proof. Core thermomechanical equipment has mastered and has relatively low metal content. Results of calculation are showing that nuclear unit with steam-coolant fast neutron reactor is more efficient than widely used unit with reactor VVER. Usage of simple scheme with four regenerative feedwater heaters the absolute efficiency ratio is more than 43%.

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