Персона:
Апсэ, Владимир Александрович

Научные группы

Научная группа

Лаборатория инновационных ядерных реакторов (Кафедра №5)

Организационные подразделения

Организационная единица

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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Апсэ

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Владимир Александрович

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Теперь показываю 1 - 10 из 26

Открытый доступ
Assessment of a possibility to use 232U in radioisotope thermoelectric generators
(2020) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© Published under licence by IOP Publishing Ltd.The paper analyzes advantages and drawbacks of the radioisotope thermoelectric generators (RTG) based on application of 238Pu and 232U. Currently, the RTG on 238Pu are widely used for long-term autonomous power supply of spaceships due to the following positive properties of 238Pu: high specific heat generation rate, long half-life, weak emission of neutrons and ?-rays. Isotope 238Pu may be produced by neutron irradiation of 237Np (main component of transuranium radioactive wastes) in nuclear reactors. The paper considers application of 232U for the same purpose because of the following positive properties of 232U: power elevation during initial 10 years of the RTG operation (effect of a and ß-emitters in 232U decay chain), long half-life (comparable with 238Pu half-life). Unfortunately, 232U decay chain includes also intense emitters of high-energy ?-rays. As a compromise, a possibility is considered to create the RTG based on mixture of 238Pu with small (below 5%) additive of 232U. Such RTG will be able to keep long-term stable operation at high power level. The following two-step technology is proposed to produce 232U: generation of 231Pa in thorium blanket of hybrid thermonuclear reactors and subsequent neutron irradiation of 231Pa in nuclear reactors till accumulation of significant 232U quantities.
Открытый доступ
The problem of large-scale production of plutonium-238 for autonomous energy sources
(2020) Shmelev, A. N.; Geraskin, N. I.; Kulikov, G. G.; Kulikov, E. G.; Apse, V. A.; Glebov, V. B.; Гераскин, Николай Иванович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич; Апсэ, Владимир Александрович; Глебов, Василий Борисович
© Published under licence by IOP Publishing Ltd.The article is devoted to the urgent problem of large-scale production of plutonium-238. Various starting isotopes and Pu-238 production schemes are analyzed. The isotope characteristics of the chain based on the starting Np-237 isotope are presented. It has been substantiated that the region of neutron resonant absorption for the isotope Np-237 is the preferred spectrum of its irradiation. It is proposed to form a region with a preferred neutron spectrum in the fast reactor core for irradiation of neptunium-237. The preferred spectrum is achieved by a heterogeneous target structure including neptunium-237 and a moderator with a high atomic weight (Pb, Pb-208, Bi, Pb-Bi eutectic). It is shown that when a moderator with a high atomic weight is used, it becomes possible to form an extensive region with the preferred spectrum. In conclusion, the main conditions for the large-scale production of isotopically pure Pu-238 in a fast reactor are formulated.
Открытый доступ
Physical aspects for involvement of thermonuclear reactors into nuclear power systems
(2020) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© Published under licence by IOP Publishing Ltd.The paper analyzes a possibility to involve hybrid thermonuclear reactors into the existing nuclear power systems. The possibility is related with production of non-traditional nuclear fuel in thorium blanket of hybrid thermonuclear reactors on D-T plasma. Non-traditional peculiarity of such a fuel consists in significant amounts of some non-traditional isotopes, namely231Pa and232U, together with traditional uranium isotope233U in the fuel. High-energy (14.1 MeV) thermonuclear neutrons can provide accumulation of significant231Pa and232U quantities through threshold (n,2n) and (n,3n) reactions. The promising features of the non-traditional fuel composition for nuclear power thermal reactors, basic component of the existing world-wide nuclear power industry, are defined by the following factors. As is known, 233U is able to provide more economical neutron balance in thermal reactors than235U and reactor-grade plutonium. The better neutron balance can result in higher values of the fuel breeding ratio and, as a consequence, in relaxation of the thermal reactors fuel self-sustainability problem. Isotopes231Pa and232U, being fertile and moderate fissionable nuclides, are able to stabilize time-dependent evolution of the thermal reactors power, prolong the thermal reactors lifetime through higher values of the fuel burn-up. Isotope232U, being intense a-emitter, is able to prevent any attempts for unauthorized usage of233U in nuclear explosive devices, i.e.232U can strengthen regime of nuclear non-proliferation. Thus, the hybrid thermonuclear reactors on D-T plasma with thorium blanket can be involved into nuclear power systems for generation of non-traditional, very promising fuel compositions for traditional nuclear power reactors.
Открытый доступ
Possibility assessment for production of non-traditional nuclear fuel in thorium blanket of hybrid thermonuclear reactor
(2020) Kulikov, G. G.; Shmelev, A. N.; Kruglikov, A. E.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Кругликов, Антон Евгеньевич; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© Published under licence by IOP Publishing Ltd.The paper aims at studying specific peculiarities in isotope composition of thorium blanket under irradiation by fusion neutron source (FNS) in hybrid thermonuclear reactor (HTR). High-energy (14 MeV) component of neutron spectrum in thorium HTR blanket results in production of non-traditional fissile mixture including not only233U, but also231Pa232U and 234U. Extraction of such non-traditional fuel from spent Th-blanket and its utilization in traditional nuclear power reactors could increase fuel burn-up and strengthen regime of nuclear non-proliferation. The detailed investigations of these positive effects require high-precision neutron-physical analyses of thorium HTR blanket. The results obtained in these investigations are presented in the paper. The following results were obtained: the chosen model of HTR allowed us to form high-energy neutron spectrum in Th-blanket with significant fraction of 14 MeV neutrons; it was evaluated that threshold (n,2n) and (n,3n)-reactions are able to produce significant amounts of non-traditional target isotopes231Pa and232U; it was shown that accumulation of non-traditional target isotopes weakened substantially in depth of Th-blanket. So, it seems reasonable to seek for optimal thickness of Th-blanket and, thus, to find optimal loading of natural thorium.
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
On a significant deceleration of the kinetics of fast transient processes in a fast reactor О СУЩЕСТВЕННОМ ЗАМЕДЛЕНИИ КИНЕТИКИ БЫСТРЫХ ПЕРЕХОДНЫХ ПРОЦЕССОВ В ЯДЕРНОМ РЕАКТОРЕ НА БЫСТРЫХ НЕИТРОНАХ
(2020) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© 2020 Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'. All rights reserved.The kinetics of nuclear reactors is determined by the average neutron lifetime. When the inserted reactivity is more than the effective fraction of delayed neutrons, the reactor kinetics becomes very rapid. The fast reactor kinetics can be slowed down by increasing the neutron lifetime. The authors consider the possibility of using a lead isotope, 208Pb, as a neutron reflector with specific properties in the lead-cooled fast reactor. To analyze the emerging effects in a fast reactor, a point kinetics model was selected, which takes into account neutrons returning from the 208Pb reflector to the reactor core. Such specific properties of 208Pb as the high atomic weight and weak neutron absorption allow neutrons from the reactor core to penetrate deeply into 208Pb reflector, slow down in it, and have a noticeable probability to return to the reactor core and affect the chain fission reaction. The neutrons coming back from the 208Pb reflector have a long «dead-time» i.e., the sum of times when neutrons leave the reactor core entering the 208Pb reflector and then diffuse back into the reactor core. During the 'dead-time', these neutrons cannot affect the chain fission reaction. In terms of the delay time, the neutrons returning from the deep layers of the 208Pb reflector are close to the delayed neutrons. Moreover, the number of the neutrons coming back from the 208Pb reflector considerably exceeds the number of the delayed neutrons. As a result, the neutron lifetime formed by the prompt neutron lifetime and the «dead-time» of the neutrons from the 208Pb reflector can be substantially increased. This will lead to a longer reactor runaway period, which will mitigate the effects of prompt supercriticality. Thus, the use of 208Pb as a neutron reflector can significantly improve the safe fast reactor operation.
Только метаданные
Fusion neutron source as an effective producer of non-traditional nuclear fuel ТЕРМОЯДЕРНЫИ НЕИТРОННЫИ ИСТОЧНИК ― ЭФФЕКТИВНЫИ НАРАБОТЧИК НЕТРАДИЦИОННОГО ЯДЕРНОГО ТОПЛИВА
(2021) Kulikov, G. G.; Shmelev, A. N.; Kruglikov, A. E.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Кругликов, Антон Евгеньевич; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
© 2021 National Research Center Kurchatov Institute. All rights reserved.The paper aims at studying peculiarities in isotope composition of thorium blanket under irradiation by fusion neutron source (FNS) in hybrid thermonuclear reactor (HTR). High-energy (14 MeV) component of neutron spectrum in thorium HTR blanket can produce nontraditional fissile mixture including not only 233U, but also 231Pa, 232U and 234U. The extraction of such non-traditional fuel from a spent Th-blanket and its utilization in traditional nuclear power reactors could increase fuel burnup and contribute to nuclear weapon nonproliferation. The results of a comprehensive investigation of the above positive effects, which included high-precision neutronics analyses of a HTR's Th blanket, are presented. The chosen model of HTR allowed the formation of high-energy neutron spectrum in Th-blanket with significant fraction of 14-MeV neutrons; it appeared that threshold (n, 2n)- and (n, 3n)-reactions are able to produce significant amounts of non-traditional target isotopes 231Pa and 232U; it was shown that accumulation of non-traditional target isotopes weakened substantially in depth of Th-blanket. It is therefore reasonable to look for optimal thickness of Th-blanket and optimal inventory of natural thorium.
Открытый доступ
On a significant slowing-down of the kinetics of fast transient processes in a fast reactor
(2020) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич
Открытый доступ
Safety features of fast reactor with heavy atomic weight weakly neutron absorbing reflector
(2020) Kulikov, G. G.; Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Куликов, Геннадий Генрихович; Апсэ, Владимир Александрович; 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.