Персона:
Сулаберидзе, Георгий Анатольевич

Организационные подразделения

Организационная единица

Институт нанотехнологий в электронике, спинтронике и фотонике

Институт ИНТЭЛ занимается научной деятельностью и подготовкой специалистов в области исследования физических принципов, проектирования и разработки технологий создания компонентной базы электроники гражданского и специального назначения, а также построения современных приборов на её основе. Наша основная цель – это создание и развитие научно-образовательного центра мирового уровня в области наноструктурных материалов и устройств электроники, спинтроники, фотоники, а также создание эффективной инновационной среды в области СВЧ-электронной и радиационно-стойкой компонентной базы, источников ТГц излучения, ионно-кластерных технологий материалов.

Фамилия

Сулаберидзе

Имя

Георгий Анатольевич

Полная страница элемента

Результаты поиска

Теперь показываю 1 - 10 из 29

Только метаданные
Generalized Approach to Calculating the Parameters of a Quasi-Ideal Cascade with a Prescribed Number of Stages and Prescribed Concentrations of the Target Component in Outgoing Flows
(2025) Smirnov, A. Y.; Sulaberidze, G. A.; Azizov, T. E.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
Только метаданные
Security of Export Deliveries of Regenerated-Uranium Light-Water Reactor Fuel from the Standpoint of IAEA Safeguards
(2020) Blandinskii, V. Y.; Nevinitsa, V. A.; Fomichenko, P. A.; Volkov, Y. N.; Gusev, V. E.; Smirnov, A. Y.; Sulaberidze, G. A.; Волков, Юрий Николаевич; Гусев, Владислав Евгеньевич; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
© 2021, Springer Science+Business Media, LLC, part of Springer Nature.The nonproliferation of nuclear materials is the key issue in supplying nuclear fuel to foreign countries. This article discusses the use of regenerated uranium to enhance the security of exports of fresh fuel for light-water reactors. It is shown that if the removal of fuel and its replacement with, for example, natural uranium go undetected, the criminals have long periods of time available to obtain a significant amount of highly enriched uranium, having only several tens of separation devices. The nonproliferation regime can be strengthened by using regenerated uranium, which contains in its decay chain 208Tl (2.61 MeV γ-line) and is advantageously distinguished from 235U (186 keV γ-line). It is shown theoretically that by controlling the thallium content the uranium content in the fuel rods can be quickly analyzed before a fuel assembly is loaded into the core.
Открытый доступ
Objective function at optimization of separation cascades
(2019) Zeng, S.; Jiang, D.; Mustafin, A. R.; Smirnov, A. Y.; Sulaberidze, G.; Borisevich, V. D.; Мустафин, Андрей Рушанович; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич; Борисевич, Валентин Дмитриевич
© 2019 Author(s). The optimization of the parameters for separation cascades is of great importance in their designing. The optimal cascade is usually construed as an installation which allows obtaining the required amount of a marketable product at the lowest unit cost. In many situations pertaining to the case, the cascade comprising a minimum possible number of separation elements (for example, gas centrifuges) has the minimum unit cost. However, there are other criteria, optimization by which leads to another set of the cascade parameters. In this connection it seems important to analyze the objective functions used at the optimization as well as their interactions. The paper proposes a method of optimizing the cascades for the isotope separation based on genetic algorithms. The use of such optimization methods in the theory of cascades is promising because they are resistant to specifying initial approximations and practically independent of the objective function type, as well as easily adaptable to changes in the dimension of the space. These specific features are often the main problems in optimizing the parameters of separation cascades. As an example, optimizing the separation cascade with variable stage separation factors for natural uranium enrichment is considered. The optimization is performed by various criteria of efficiency. The results obtained have made it possible to compare the parameters of the cascades optimized by various criteria and to identify the relationships between them. The developed method can be adapted to optimizing various cascade options for the separation of both binary mixtures and multi-component mixtures.
Открытый доступ
Optimization of a system of square cascades for efficient concentration of intermediate isotopes
(2020) Azizov, T. E.; Smirnov, A. Yu.; Sulaberidze, G. A.; Mustafin, A. R.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич; Мустафин, Андрей Рушанович
© 2020 Published under licence by IOP Publishing Ltd.The problem of obtaining relatively high concentrations of stable isotopes of intermediate mass numbers is considered. The object of research is a connection of three ordinary square cascades. The possibility of simultaneous concentration of isotopes of intermediate masses in different output flows of cascades is shown. The dependencies of the parameters of the cascade schemes under consideration are investigated. The method of optimization of such system of square cascades according to the criterion of minimum relative total flow at given concentrations of target components is proposed. Calculations were made on the example of isotope mixtures with the number of components 4 and 5.
Только метаданные
Cascades with Flow Expansion for Simultaneous Concentration of Intermediate Components
(2019) Fomin, D. N.; Smirnov, A. Y.; Sulaberidze, G. A.; Mustafin, A. R.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич; Мустафин, Андрей Рушанович
© 2019, Springer Science+Business Media, LLC, part of Springer Nature.A cascade scheme allowing two intermediate-mass isotopes to be concentrated in a single cascade above the maximum admissible concentrations at the outputs of ordinary cascades is proposed. A cascade with two flow expansions and two additional product flows is used for this. For the example of a mixture of tungsten isotopes, it is shown that the concentrations of 183W and 184W can be increased simultaneously up to 70 and 80%, respectively. In addition, additional product flows can be equal to 50–70% of the primary (end) product flow of the cascade.
Только метаданные
Debatable issues on the derivation of the separation potential for multicomponent mixtures
(2023) Smirnov, A. Y.; Sulaberidze, G. A.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
Только метаданные
Comparison of the efficiency of square cascades with an additional product flow and double cascades to concentrate intermediate isotopes
(2022) Azizov, T. E.; Smirnov, A. Yu.; Sulaberidze, G. A.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
© 2022 Institute of Physics Publishing. All rights reserved.Original techniques were proposed for calculating and optimizing double cascades (DC) built of square cascades and a square cascade with an additional product flow (SCAP). Both cascade schemes (DC and SCAP) were tested in solving a task of simultaneous enrichment of three components of a model mixture to a pre-defined level. A comparison of the DC and SCAP efficiency was made according to the minimum of total cascade flow. The results have shown that the double cascade is more efficient in terms of the chosen criterion.
Только метаданные
Large-scale production by centrifugation of isotopically modified molybdenum for nuclear reactors and its cost evaluation
(2021) Zeng, S.; Zhao, K.; Jiang, D. J.; Borisevich, V. D.; Smirnov, A. Y.; Sulaberidze, G. A.; Борисевич, Валентин Дмитриевич; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
© 2021 Elsevier LtdMolybdenum is considered as one of the substitutes for zirconium in making fuel cladding for safe reactor designs. The isotopically modified molybdenum (IMM) should be used instead of natural molybdenum to achieve higher energy efficiency, reduce uranium consumption, and mitigate the impact on the nuclear fuel cycle. This task can be fulfilled by using the same technology of gas centrifugation for uranium enrichment to remove the isotopes in natural molybdenum with larger thermal neutron absorption cross sections. Optimized double-cascade separation schemes consisting of the Q-cascade model are employed for studying massive production of IMM and evaluating the economic feasibility of production. A simple formula is derived to be able to assess the cost per kilogram of IMM, taking into account various cost-affecting factors. The results demonstrate that it is feasible to produce massively the IMM with a total thermal neutron absorption cross section equivalent to that of zirconium.
Только метаданные
Efficiencies of a Nonmixing (Ideal) Cascade and a Mixing Cascade with Separation Coefficients Dependent on the Parameters of a Cascade Stage
(2024) Mustafin, A.R.; Smirnov, A.Yu.; Sulaberidze, G.A.; Мустафин, Андрей Рушанович; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
Только метаданные
A method for purifying reprocessed uranium from even isotopes under conditions of multiple recycle
(2022) Palkin, V. A.; Smirnov, A. Y.; Chistov, A. V.; Sulaberidze, G. A.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич
© 2022 Korean Nuclear SocietyWe proposed a modification of a double cascade scheme to enrich reprocessed uranium. Such a cascade scheme represents a combination of one cascade with “broadening” of the flow and an ordinary three-flow cascade. A calculation and optimization method has been developed for the proposed scheme according to various efficiency criteria. It is shown that the proposed scheme makes it possible to obtain low-enriched uranium of commercial quality using reprocessed uranium of different initial compositions. For example, the enrichment of reprocessed uranium, which had gone through five consequent recycles, was considered. The proposed scheme allowed to enrich it with simultaneous fulfillment of restrictions on isotopes 232U, 234U, and 236U. Such results indicate the scheme's applicability under conditions of multiple recycling of uranium in reactor fuel. Computational experiments have shown that in the proposed modification, a noticeable saving of natural uranium in the cycle (∼18%) can be achieved, provided that the additional consumption of separative work does not exceed 10%, compared with the case of enrichment of natural uranium to obtain LEU of equivalent quality.