Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap / A. V. Arzhannikov, V. N. Shmakov, D. G. Modestov [et al.]

Уровень набора: Nuclear Engineering and TechnologyАльтернативный автор-лицо: Arzhannikov, A. V., Andrey Vasilyevich;Shmakov, V. N., Vladimir Mikhaylovich;Modestov, D. G., Dmitry Gennadjevich;Bedenko, S. V., physicist, Associate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences, 1980-, Sergey Vladimirovich;Prikhodko, V. V., Vadim Vadimovich;Lutsik, I. O., Igor Olegovich;Shamanin, I. V., specialist in the field of nuclear physics, Professor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences, specialist in the field of nuclear power engineering, 1962-, Igor VladimirovichКоллективный автор (вторичный): Национальный исследовательский Томский политехнический университет, Инженерная школа ядерных технологий, Отделение ядерно-топливного циклаЯзык: английский.Страна: .Резюме или реферат: To study the thermophysical and neutronic properties of thorium-plutonium fuel, a conceptual design of a hybrid facility consisting of a subcritical Th–Pu reactor core and a source of additional D-D neutrons that places on the axis of the core is proposed. The source of such neutrons is a column of high-temperature plasma held in a long magnetic trap for D-D fusionreactions. This article presents computer simulation results of generation of thermonuclear neutrons in the plasma, facility neutronic properties and the evolution of a fuel nuclide composition in the reactor core. Simulations were performed for an axis-symmetric radially profiled reactor core consisting of zones with various nuclear fuel composition. Such reactor core containing a continuously operating stationary D-D neutron source with a yield intensity of Y = 2 ? 1016 neutrons per second can operate as a nuclear hybrid system at its effective coefficient of neutron multiplication 0.95–0.99. Options are proposed for optimizing plasma parameters to increase the neutron yield in order to compensate the effective multiplication factor decreasing and plant power in a long operating cycle (3000-day duration). The obtained simulation results demonstrate the possibility of organizing the stable operation of the proposed hybrid ‘fusion–fission’ facility..Примечания о наличии в документе библиографии/указателя: [References: 39 tit.].Тематика: электронный ресурс | труды учёных ТПУ | thorium sub-critical assembly | fusion neutron source | hybrid fusion-fission reactor | термоядерные реакторы | термоядерные источники Ресурсы он-лайн:Щелкните здесь для доступа в онлайн
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[References: 39 tit.]

To study the thermophysical and neutronic properties of thorium-plutonium fuel, a conceptual design of a hybrid facility consisting of a subcritical Th–Pu reactor core and a source of additional D-D neutrons that places on the axis of the core is proposed. The source of such neutrons is a column of high-temperature plasma held in a long magnetic trap for D-D fusionreactions. This article presents computer simulation results of generation of thermonuclear neutrons in the plasma, facility neutronic properties and the evolution of a fuel nuclide composition in the reactor core. Simulations were performed for an axis-symmetric radially profiled reactor core consisting of zones with various nuclear fuel composition. Such reactor core containing a continuously operating stationary D-D neutron source with a yield intensity of Y = 2 ? 1016 neutrons per second can operate as a nuclear hybrid system at its effective coefficient of neutron multiplication 0.95–0.99. Options are proposed for optimizing plasma parameters to increase the neutron yield in order to compensate the effective multiplication factor decreasing and plant power in a long operating cycle (3000-day duration). The obtained simulation results demonstrate the possibility of organizing the stable operation of the proposed hybrid ‘fusion–fission’ facility.

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