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Апсэ, Владимир Александрович

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Научная группа

Лаборатория инновационных ядерных реакторов и ядерных топливных циклов (Кафедра №5 ИЯФиТ)

Организационные подразделения

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Цель ИЯФиТ и стратегия развития - создание и развитие научно-образовательного центра мирового уровня в области ядерной физики и технологий, радиационного материаловедения, физики элементарных частиц, астрофизики и космофизики.

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Владимир Александрович

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Только метаданные
Proliferation-protected, ultra-high burn-up reactor fuel produced in the thorium blanket of a fusion neutron source
(2020) Kulikov, G. G.; Shmelev, A. N.; Kulikov, E. G.; Apse, V. A.; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич; Апсэ, Владимир Александрович
Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference.All rights reserved.This paper aims at finding solutions of so important problems of nuclear power as decreasing the scope and the number of technological operations, as well as enhancing the proliferation resistance of fissile materials in nuclear fuel cycle by means of minimal changes in the cycle. The method is including fusion neutron sources with thorium blanket into future nuclear power system. In addition to production of light uranium fraction consisting of 233U and 234U, high-energy 14-MeV neutrons emitted in the process of fusion (D,T)-reaction can generate 231Pa and 232U through (n,2n)- and (n,3n)reactions. It has been demonstrated that admixture of 231Pa into fresh fuel composition can stabilize its neutron-multiplying properties thanks to two well-fissile consecutive isotopes 232U and 233U, products of radiative neutron capture by 231Pa. Coupled system of two well-fissile isotopes can allow us to reach the following goals: the higher fuel burn-up and, as a consequence, the longer fuel lifetime; the shorter scope and the lower number of technological operations in nuclear fuel cycle; the better economic potential of nuclear power technologies.
Только метаданные
PROLIFERATION PROTECTION OF URANIUM DUE TO THE PRESENCE OF 232U DECAY PRODUCTS AS INTENSE SOURCES OF HARD GAMMA RADIATION ПРИЧИНЫ ЖЕСТКОГО ГАММА-ИЗЛУЧЕНИЯ В ЦЕПОЧКЕ РАСПАДА 232U, ЗАЩИЩАЮЩЕИ УРАН ОТ НЕКОНТРОЛИРУЕМОГО ИСПОЛЬЗОВАНИЯ
(2022) Genrikhovich, K. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© 2022 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The purpose of the article is to show the nuclear-physical causes of hard γ-quanta in the uranium-232 decay chain, to propose tactics for handling uranium containing uranium-232, and to assess the magnitude of its protective γ-barrier against uncontrolled use of uranium. The authors show the general picture of the decays of the chain of nuclide transformations of uranium-232, on which the protection of uranium from its uncontrolled use is based. During the decay of nuclei, their emission of α- or β-particles is only the first stage of the most complex process of rearrangement of both the internal structure of the nucleus itself, which consists in the rearrangement of the neutron and proton shells and the levels of its excitation, and in the rearrangement of the electron shells of the atom. As a rule, the daughter nucleus is in a highly excited state, which is removed by the emission of hard γ-quanta and internal conversion electrons. After the second case, the remaining excitation of the atom is removed by the emission of characteristic γ-quanta and Auger-electrons with characteristic γ -quanta. In addition, explanations are given for the quantum-mechanical reasons for the hard γ-radiation of thallium-208 and bismuth-212, which complete the decay chain of uranium-232. The authors also proposed a tactic for handling uranium containing uranium-232. Since the hard γ-quanta of thallium-208 and bismuth-212 appear only at the end of the decay chain of uranium-232, after its chemical purification from its decay products, uranium-232 itself does not pose a radiation hazard; therefore, at this time it is advisable to conduct all necessary operations for transporting the material to the plant, fabricating uranium-based fuel containing uranium-232, and transporting this fuel to the nuclear facility where it will be used.
Только метаданные
Proliferation protection of uranium due to the presence of U-232 decay products as intense sources of hard gamma radiation
(2022) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
Только метаданные
Comprehensive analysis of proliferation protection of uranium due to the presence of 232U and its decay products
(2022) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
Только метаданные
Favorable Effects of an Inner Lead Cavity on Neutronic Physics of a Lead-Cooled Fast Reactor
(2020) Shmelev, A. N.; Apse, V. A.; Kulikov, G. G.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
© 2020, Pleiades Publishing, Ltd.Abstract: The paper considers the effects produced by arranging a lead cavity in the central part of a lead-cooled fast reactor core. It is shown that the most favorable effect from the presence of an inner lead cavity at the center of the core can be obtained when radiogenic lead with a dominant 208Pb isotope content is used as the material of the cavity, coolant, and neutron reflector. This is explained by the extremely low neutron absorption of 208Pb in a wide range of neutron energies. If the thickness of the 208Pb inner cavity is chosen properly, then a spectral region with the prevailing share of resonance, epithermal, and thermal neutrons is created in the cavity. This results in a sharp increase in the mean prompt neutron lifetime (by few orders of magnitude) and enhancement of the stabilizing Doppler effect. The neutron migration from the inner cavity to the reactor core is able to intensify the fission chain reaction (FCR) and contribute positively to reactor reactivity. In addition, the high flux of slowed neutrons in the inner 208Pb-cavity makes it possible to expect efficient transmutation of long-lived fission products.
Только метаданные
Advantages of a Fast Reactor Core Surrounded by a Physically Thick Neutron Reflector Made of Lead-208
(2020) Shmelev, A. N.; Apse, V. A.; Kulikov, G. G.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
© 2020, Pleiades Publishing, Ltd.Abstract: In the paper, the influence of replacement of natural lead with lead-208 as a coolant and fast reactor reflector on its neutron-physical parameters is considered. The possibility of significantly increasing the mean prompt neutron lifetime by using lead-208 is shown. It is proposed to place a layer containing a neutron absorber over the core in its reflector to control the reactor reactivity. It is shown that when using lead-208, the efficiency of this layer is noticeably higher, and the Doppler effect is enhanced than when using natural lead.
Только метаданные
Evaluating Conditions and Possibilities for Neutron Catalysis of Thermonuclear Reactions in Three-Component (D–T–3He)-Plasma
(2022) Shmelev, A. N.; Geraskin, N. I.; Apse, V. A.; Glebov, V. B.; Kulikov, G. G.; Kulikov, E. G.; Гераскин, Николай Иванович; Апсэ, Владимир Александрович; Глебов, Василий Борисович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич
Только метаданные
Potential role of fusion neutron source in nuclear power systems ПОТЕНЦИАЛЬНАЯ РОЛЬ ТЕРМОЯДЕРНОГО НЕИТРОННОГО ИСТОЧНИКА В ЯДЕРНЫХ ЭНЕРГЕТИЧЕСКИХ СИСТЕМАХ
(2021) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© 2021 National Research Center Kurchatov Institute. All rights reserved.The paper analyzes the possibility of integrating hybrid thermonuclear reactors (HTRs) into existing nuclear power systems. This is supposed to involve the production of non-traditional nuclear fuel in a D-T-plasma operated HTR with a thorium blanket. Non-traditional fuel to be produced is peculiar in that it contains in significant amounts of rare isotopes, such as 231Pa and 232U, alongside the traditional 233U. High-energy (14.1 MeV) thermonuclear neutrons have a unique ability to promote the accumulation of significant amounts of 231Pa and 232U via threshold (n, 2n)- and (n, 3n)-reactions. Non-traditional fuel compositions for nuclear power thermal reactors (the most common nuclear reactor class in the world), hold promise due to the following factors. As is known, the neutron balances for reactors fueled with 235U are better (in terms of the breeding ratio enhancement) than for reactors fueled with 233U or reactor-grade plutonium. A better neutron balance is likely to translate into higher fuel breeding ratios and help ease the thermal reactors' fuel self-sustainability problem. Because 231Pa and 232U are fertile and moderately fissionable nuclides, they can stabilize the time-dependent behavior of the thermal reactor power and prolonging a thermal reactor's lifetime through higher fuel burnup. Being a strong α-emitter, 232U can be used to control unauthorized use of 233U-based nuclear explosives and thereby contribute to nuclear non-proliferation. All this suggests that D-T-plasma operated HTRs with a thorium blanket can be integrated into nuclear power systems to generate very promising nontraditional fuel compositions for conventional nuclear power reactors.
Только метаданные
Safety of a fast reactor with a reflector containing a moderator with heavy atomic weight and weak neutron absorption БЕЗОПАСНОСТЬ БЫСТРОГО РЕАКТОРА С ОТРАЖАТЕЛЕМ, СОДЕРЖАЩИМ ЗАМЕДЛИТЕЛЬ С БОЛЬШИМ АТОМНЫМ ВЕСОМ И МАЛЫМ ПОГЛОЩЕНИЕМ НЕИТРОНОВ
(2019) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© 2019 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The purpose of the study is to justify the possibility of improving the safety of fast reactors by surrounding their cores with reflectors made of material with special neutron#physical properties. Such properties of the 208Pb lead isotope as heavy atomic weight, small absorption cross section, and high inelastic scattering threshold lead to some peculiarities in neutron kinetics of the fast reactor with a 208Pb reflector, which can significantly improve the reactor safety. The reflector will also make it possible to generate additional delayed neutrons, which are characterized by «dead» time. This will increase the resistibility of the fission chain reaction to reactivity jumps and exclude prompt supercriticality. Note that the additional delayed neutrons can be generated by the reactor designers. The relevance of the study is that the generation of additional delayed neutrons in the reflector will make it possible to reduce the consequences of a reactivity accident even if the reactivity introduced exceeds the effective fraction of delayed neutrons. At the same time, the role of the fraction of delayed neutrons as the maximum permissible reactivity for reactor safety is depreciated. The scientific novelty of the study is that the problem of the formation of additional neutrons, which in their properties are close to traditional delayed neutrons, has not been posed so far. The authors propose a new method for improving the safety of fast reactors by replenishing the fraction of delayed neutrons due to the time delay of prompt neutrons during their transfer in the reflector. To implement the considered advantages, the following combination is acceptable: lead enriched by 208Pb is used as a neutron reflector while natural lead or other material (sodium, etc.) is used as a coolant in the reactor core.
Только метаданные
COMPREHENSIVE ANALYSIS OF PROLIFERATION PROTECTION OF URANIUM DUE TO THE PRESENCE OF 232U AND ITS DECAY PRODUCTS [КОМПЛЕКСНЫИ АНАЛИЗ ЗАЩИЩЕННОСТИ УРАНА БЛАГОДАРЯ НАЛИЧИЮ В НЕМ 232U И ПРОДУКТОВ ЕГО РАСПАДА]
(2022) Genrikhovich, K. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич