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RISS 인기검색어
- 검색키워드
- 저자 : Vadim V. Prikhodko (검색결과 3 건)
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Arzhannikov, Andrey V.,Shmakov, Vladimir M.,Modestov, Dmitry G.,Bedenko, Sergey V.,Prikhodko, Vadim V.,Lutsik, Igor O.,Shamanin, Igor V. Korean Nuclear Society 2020 Nuclear Engineering and Technology Vol.52 No.11
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 × 10<sup>16</sup> 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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Bedenko, Sergey V.,Arzhannikov, Andrey V.,Lutsik, Igor O.,Prikhodko, Vadim V.,Shmakov, Vladimir M.,Modestov, Dmitry G.,Karengin, Alexander G.,Shamanin, Igor V. Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.6
The results of full-scale numerical experiments of a hybrid thorium-containing fuel cell facility operating in a close-to-critical state due to a controlled source of fusion neutrons are discussed in this work. The facility under study was a complex consisting of two blocks. The first block was based on the concept of a high-temperature gas-cooled thorium reactor core. The second block was an axially symmetrical extended plasma generator of additional neutrons that was placed in the near-axial zone of the facility blanket. The calculated models of the blanket and the plasma generator of D-T neutrons created within the work allowed for research of the neutronic parameters of the facility in stationary and pulse-periodic operation modes. This research will make it possible to construct a safe facility and investigate the properties of thorium fuel, which can be continuously used in the epithermal spectrum of the considered hybrid fusion-fission reactor.
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Neutronic and thermohydraulic blanket analysis for hybrid fusion-fission reactor during operation
Sergey V. Bedenko,Igor O. Lutsik,Vadim V. Prikhodko,Anton A. Matyushin,Sergey D. Polozkov,Vladimir M. Shmakov,Dmitry G. Modestov,Hector Rene Vega-Carrillo Korean Nuclear Society 2023 Nuclear Engineering and Technology Vol.55 No.7
This work demonstrates the results of full-scale numerical experiments of a hybrid thorium-containing fuel plant operating in a state close to critical due to a controlled source of D-T neutrons. The proposed facility represented a level of generated power (~10-100 MW<sub>t</sub>) in a small pilot. In this work, the simulation of the D-T neutron plasma source operation in conjunction with the facility blanket was performed. The fission of fuel nuclei and the formation of spatial-energy release were studied in this simulation, in pulsed and stationary modes of the facility operation. The optimization results of neutronic and fluid dynamics studies to level the emerging offsets of the radial energy formed in the volume of the facility multiplying part due to the pulsed operation of the D-T neutron plasma source were presented. The results will be useful in improving the power control-based subcriticality monitoring method in coupled systems of the "pulsed neutron source-subcritical fuel assembly" type.
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