Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap

Andrey V. Arzhannikov, Vladimir M. Shmakov, Dmitry G. Modestov, Sergey V. Bedenko, Vadim V. Prikhodko, Igor O. Lutsik, Igor V. Shamanin

Результат исследований: Материалы для журналаСтатья

Аннотация

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.

Язык оригиналаАнглийский
Страницы (с-по)2460-2470
Число страниц11
ЖурналNuclear Engineering and Technology
Том52
Номер выпуска11
DOI
СостояниеОпубликовано - ноя 2020

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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