Персона: Гусев, Владислав Евгеньевич
Загружается...
Email Address
Birth Date
Научные группы
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.
Статус
Фамилия
Гусев
Имя
Владислав Евгеньевич
Имя
7 results
Результаты поиска
Теперь показываю 1 - 7 из 7
- ПубликацияТолько метаданныеSecurity 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.
- ПубликацияТолько метаданныеPhysical and Technical Problems of Reprocessed Uranium Enrichment with Repeated Recycling in Light-Water Reactors and Ways to Solve Them(2020) Nevinitsa, V. A.; Bobrov, E. A.; Belov, I. A.; Rodionova, E. V.; Smirnov, A. Y.; Gusev, V. E.; Sulaberidze, G. A.; Смирнов, Андрей Юрьевич; Гусев, Владислав Евгеньевич; Сулаберидзе, Георгий Анатольевич© 2020, Springer Science+Business Media, LLC, part of Springer Nature.Issues concerning fuel cycle closure are discussed. It is shown that from the standpoint of full utilization of reprocessed nuclear materials the main problems are associated with repeated recycling of uranium, the reason being that limitations are imposed on the content of the isotope 232U in fresh fuel produced from reprocessed materials. The losses of the isotope 235U on repeated recycling of reprocessed uranium in the form of fuel from uranium regenerate and mixtures of processed uranium and plutonium oxides are evaluated. For a light-water reactor, a method of fuel cycle closure making it possible to reduce the 235U losses almost to zero on purification of reprocessed uranium from 232U is shown.
- ПубликацияТолько метаданныеOn the problems of reusing reprocessed uranium by enrichment in schemes based on ordinary cascades(2022) Gusev, V. E.; Гусев, Владислав Евгеньевич© 2022 Institute of Physics Publishing. All rights reserved.The problem of spent nuclear fuel attracts considerable attention while its quantity is accumulating worldwide. The problem of long-term supply of the fresh fuel also remains important. One of the strategies to solve both problems is reusing the spent nuclear material. The uranium, in this way, could be recycled multiple times in light-water reactors. In order to recycle the uranium, it is extracted from the irradiated fuel during the reprocessing and then enriched in 235U, taking into account the limitations on reactor-born isotopes 232,236U in the final product. The only way to do this is enrichment in cascades of gas centrifuges. However, not every cascade scheme is able to re-enrich the uranium for multiple recycles, utilizing the whole amount of uranium extracted from the irradiated fuel each time. This study shows that configurations based on ordinary three-flow cascades could not be used for this purpose. In particular, we have shown that starting from the second uranium fuel cycle, such schemes are no longer able to reclaim the necessary proportion of the reprocessed uranium.
- ПубликацияТолько метаданныеDevelopment of schemes from a single cascade to multi-cascades for separation of regenerated uranium(2023) Zeng, S.; Smirnov, A. Yu.; Borisevich, V. D.; Sulaberidze, G. A.; Gusev, V. E.; Смирнов, Андрей Юрьевич; Борисевич, Валентин Дмитриевич; Сулаберидзе, Георгий Анатольевич; Гусев, Владислав Евгеньевич
- ПубликацияТолько метаданныеThe Efficiency of Using Double Cascades with a Carrier Gas for Enriching Reprocessed Uranium Under the Conditions of a Multiple Recycle(2023) Smirnov, A. Y.; Nevinitsa, V. A.; Sulaberidze, G. A.; Gusev, V. E.; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич; Гусев, Владислав Евгеньевич
- ПубликацияТолько метаданныеAnalysis of the Effect of Restrictions on Isotopes U-232,U-234,U-236 in Marketable LEU on the Choice of Methods for Enriching Reprocessed Uranium in Cascades of Centrifuges(2021) Smirnov, A. Y.; Gusev, V. E.; Sulaberidze, G. A.; Nevinitsa, V. A.; Смирнов, Андрей Юрьевич; Гусев, Владислав Евгеньевич; Сулаберидзе, Георгий АнатольевичThe study addresses the problems of reprocessed uranium re-enrichment. It is shown that, in the most general formulation, the problem of reprocessed uranium re-enrichment that meets all the requirements on the content of even isotopes and the conditions of spending a given amount of initial reprocessed uranium for production of unit mass of the product cannot be solved in a three-flow cascade of centrifuges or in the simplest versions of double cascades. The possibility of solving the formulated problem in a modified double cascade scheme with a low-enriched uranium (LEU) diluter is demonstrated. The results of numerical experiments showed that it is possible to obtain marketable LEU in the studied version of the double cascade after spending a given amount of reprocessed uranium and meeting different constraints on U-232 concentration in the product, including even stricter constraints than those currently accepted at separation plants.
- ПубликацияТолько метаданныеMethod for utilizing contaminated fractions of reprocessed uranium enrichment in double cascade schemes(2025) Gusev, V. E.; Smirnov, A. Yu.; Sulaberidze, G. A.; Гусев, Владислав Евгеньевич; Смирнов, Андрей Юрьевич; Сулаберидзе, Георгий Анатольевич