Персона: Куликов, Евгений Геннадьевич
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Институт ядерной физики и технологий
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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Евгений Геннадьевич
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- ПубликацияТолько метаданныеPotential 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.
- ПубликацияТолько метаданныеUsing (Np, Am) Fractions of Minor Actinides for 238Pu Production in a VVER-Type Reactor(2024) 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
- ПубликацияОткрытый доступОценка возможности крупномасштабной наработки 238 Pu в энергетическом реакторе типа ВВЭР-1000(НИЯУ МИФИ, 2023) Шмелёв, А. Н.; Апсэ, Владимир Александрович; Куликов, Геннадий Генрихович; Куликов, Евгений Геннадьевич; Глебов, Василий Борисович; Гераскин, Николай ИвановичПриведены расчетные оценки принципиальной возможности крупномасштабной наработки 238 Pu в активной зоне энергетического реактора типа ВВЭР-1000. Предлагается использовать Np-фракцию младших актинидов из состава трансурановых радиоактивных отходов в качестве стартового материала. Облучательное устройство с NpO2 -твэлами размещается в центре активной зоны реактора. Варьирование шага решетки NpO2-твэлов и окружение облучательного устройства слоем тяжелого замедлителя применяется с целью создания оптимальных спектральных условий для крупномасштабной (~ 3 кг/г.) наработки кондиционного плутония с требуемым изотопным составом (не менее 85% 238 Pu и не более 2 ppm 236Pu). Плутоний такого изотопного состава пригоден для использования в качестве теплового источника в радиоизотопных термоэлектрических генераторах и в кардиостимуляторах. Показано, что расчетные масштабы наработки 238 Pu в энергетическом реакторе типа ВВЭР значительно превосходят имеющиеся масштабы его наработки в исследовательских реакторах
- ПубликацияОткрытый доступОбоснование физических характеристик и защищенности уран-ториевого оксидного топлива легководного реактора со сверхкритическими параметрами теплоносителя(НИЯУ МИФИ, 2010) Куликов, Е. Г.; Куликов, Евгений Геннадьевич; Шмелев, А. Н.
- ПубликацияТолько метаданныеEvaluating 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
- ПубликацияОткрытый доступClosed nuclear fuel cycle of thermal and fast reactors with fuel self-sufficiency(НИЯУ МИФИ, 2025) Shmelev, A. N.; Apse, V. A.; Kulikov, E. G.; Kulikov, G. G.; Glebov, V. B.; Глебов, Василий Борисович; Куликов, Евгений Геннадьевич; Куликов, Геннадий Генрихович; Апсэ, Владимир АлександровичThe paper presents the results obtained in numerical evaluations of a possibility to reach self-sufficiency of fissile materials in the joint system of fast and thermal reactors. These studies considered the joint system consisting of thermal light-water reactors of VVER-type and fast lead-cooled reactors of BREST-type, which are operated within the frames of the closed (Th-U-Pu) fuel cycle. It was assumed that fast reactors (FR) of BREST-type used the mixed thorium-plutonium nitride fuel, while thermal reactors (TR) of VVER-type used the mixed oxide fuel of natural uranium and 233U. Uranium isotope 233U was produced in the Th-fraction of FR fuel for further introduction into the fresh composition of TR fuel, while plutonium was produced in the natural uranium fraction of TR fuel for further introduction into the fresh composition of FR fuel. The numerical studies resulted in the determination of the conditions necessary to provide fuel self-sufficiency in the joint TR-FR system. The following key findings of the research may be noted: – It is demonstrated the possibility to create the joint TR-FR system with inherent fuel self-sufficiency; – Involvement of thorium and 233U in the closed NFC of the joint TR-FR system can arrange an optimal regime for production and consumption of main FM; – Purposeful change of thermal power and introduction of natural uranium in the fuel composition of BREST-type FR made it possible to reach fuel self-sufficiency of the joint TR-FR system; – Application of radiogenic lead instead of natural lead allowed us to reduce necessary values of thermal power and content of natural uranium nitride in the fuel of BREST-type FR.
- ПубликацияОткрытый доступEnvironmental protection in closed nuclear fuel cycle and nuclear weapons non-proliferation problem(НИЯУ МИФИ, 2014) Apse, V. A.; Shmelev, A. N.; Kulikov, E. G.; Kulikov, G. G.; Куликов, Евгений Геннадьевич; Куликов, Геннадий Генрихович; Апсэ, Владимир Александровичllowing two points of view, namely negative ecological effects of the open and closed NFC on the environment, and increased threats to proliferation of fissile materials which could be used to manufacture nuclear explosive devices (NED). Main stages of the closed NFC, starting from mining and primary treatment of uranium ores and ending by ultimate disposal of radioactive wastes (RAW) from radiochemical reprocessing of spent nuclear fuel (SNF), are briefly characterized. The textbook presents some results obtained in numerical evaluations of the effects produced at various stages of the closed NFC on human health, on the environment, and on a possibility to divert fissile materials from peaceful energy applications to terrorist purposes. The most promising strategies for energy utilization of reactor-grade plutonium and weapon-grade plutonium in nuclear power reactors at NPP are analyzed with accounting for potential applicability of reactor-grade plutonium as a NED charge. The textbook underlines a reasonability to use isotopic denaturing of uranium and plutonium for reliable non-proliferation of nuclear weapons. The textbook is intended for training of the specialists in nuclear technologies, operation of NFC facilities and nuclear non-proliferation. The textbook was prepared and published at the expense of the International Science and Technology Center (ISTC) within the frames of the Responsible Science Program of Sub-Program SB159 “Culture of Nuclear Non-Proliferation”.
- ПубликацияТолько метаданныеPROLIFERATION 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.
- ПубликацияТолько метаданныеProliferation-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 АлександровичCopyright © 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.
- ПубликацияОткрытый доступНейтронно-физические основы масштабной наработки 238Pu для автономных источников энергии(2023) Шмелев, А. Н.; Апсэ, Владимир Александрович; Куликов, Евгений Геннадьевич; Куликов, Геннадий Генрихович; Глебов, Василий БорисовичРассмотрены нейтронно-физические основы масштабной наработки изотопа 238Pu для автономных источников энергии. Изотоп 238Pu является уникальным источником длительного автономного энергоснабжения в различных устройствах для удаленных районов Земли и в космосе. Имеющиеся в настоящее время в России и мире мощности по его наработке недостаточны. В работе рассматриваются цепочки наработки изотопа 238Pu и устанавливаются оптимальные спектр и поток нейтронов для его наработки. Делается вывод, что наиболее привлекательным стартовым изотопом является 237Np, который может быть извлечен из облученного ядерного топлива. Предлагаемый метод позволяет говорить о масштабной наработке плутония, отличающегося высоким содержанием изотопа 238Pu и низким содержанием изотопа 236Pu.