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005 20231030041816.0
035 _a(RuTPU)RU\TPU\network\33417
035 _aRU\TPU\network\28811
090 _a662280
100 _a20200707a2020 k y0rusy50 ba
101 0 _aeng
102 _aNL
135 _adrnn ---uucaa
181 0 _ai
182 0 _ab
200 1 _aFacility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap
_fA. V. Arzhannikov, V. N. Shmakov, D. G. Modestov [et al.]
203 _aText
_celectronic
300 _aTitle screen
320 _a[References: 39 tit.]
330 _aTo 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.
461 _tNuclear Engineering and Technology
463 _tVol. 52, iss. 11
_v[P. 2460-2470]
_d2020
610 1 _aэлектронный ресурс
610 1 _aтруды учёных ТПУ
610 1 _athorium sub-critical assembly
610 1 _afusion neutron source
610 1 _ahybrid fusion-fission reactor
610 1 _aтермоядерные реакторы
610 1 _aтермоядерные источники
701 1 _aArzhannikov
_bA. V.
_gAndrey Vasilyevich
701 1 _aShmakov
_bV. N.
_gVladimir Mikhaylovich
701 1 _aModestov
_bD. G.
_gDmitry Gennadjevich
701 1 _aBedenko
_bS. V.
_cphysicist
_cAssociate Professor of Tomsk Polytechnic University, Candidate of physical and mathematical sciences
_f1980-
_gSergey Vladimirovich
_2stltpush
_3(RuTPU)RU\TPU\pers\30831
701 1 _aPrikhodko
_bV. V.
_gVadim Vadimovich
701 1 _aLutsik
_bI. O.
_gIgor Olegovich
701 1 _aShamanin
_bI. V.
_cspecialist in the field of nuclear physics
_cProfessor of Tomsk Polytechnic University, Doctor of physical and mathematical sciences
_cspecialist in the field of nuclear power engineering
_f1962-
_gIgor Vladimirovich
_2stltpush
_3(RuTPU)RU\TPU\pers\30832
712 0 2 _aНациональный исследовательский Томский политехнический университет
_bИнженерная школа ядерных технологий
_bОтделение ядерно-топливного цикла
_h7864
_2stltpush
_3(RuTPU)RU\TPU\col\23554
801 2 _aRU
_b63413507
_c20200930
_gRCR
856 4 _uhttps://doi.org/10.1016/j.net.2020.05.003
942 _cCF