Персона: Волков, Юрий Николаевич
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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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Юрий Николаевич
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- ПубликацияТолько метаданныеVoid Reactivity Effect in the MTIR-SKD Multipurpose Test Research Reactor(2025) Lapin, A. S.; Volkov, Y. N.; Subbotin, S. A.; Волков, Юрий Николаевич; Субботин, Станислав Анатольевич
- 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.
- ПубликацияОткрытый доступProliferation resistance analysis of LWR fuel in terms of IAEA safeguards implementation(2019) Nevinitsa, V.; Gusev, V.; Smirnov, A.; Volkov, Y.; Гусев, Владислав Евгеньевич; Смирнов, Андрей Юрьевич; Волков, Юрий Николаевич© 2019 Author(s). Nuclear power industry could be truly sustainable only under the condition of the Treaty on the Non- Proliferation of Nuclear Weapons. Thus, the issue of nuclear materials illicit diversion is crucial. One possible way to increase the resistance of the nuclear system to proliferation could be the increase of inherent security of nuclear materials used. One of the practical steps here could be the creation of intrinsic barriers in low-enriched uranium (LEU) fuel that is used in light water reactors worldwide. By the way, not only natural uranium could be used as raw material for such LEU, but also reprocessed uranium produced from spent nuclear fuel. In this study, proliferation resistance of enriched reprocessed uranium (in other words, commercial LEU made of reprocessed uranium) in the case of its covert diversion was analyzed. The conditions, under which this material could be turned into a direct use material in terms of IAEA was outlined. The scale of enrichment facility required to produce a significant quantity (SQ) of highly enriched uranium (HEU) throughout the duration of three months to two years, having the predetermined amount of diverted material (one SQ of LEU stolen from fresh fuel) was also assessed. Then, it was shown that such a feature of fuel made of reprocessed uranium as 232 U presence makes the detection of potential diversion possible even for much smaller quantities of LEU than in the case of fuel made of natural uranium.
- ПубликацияОткрытый доступEnhancing the efficiency of the MOX fuel cycle for VVER-1200 using burnable absorbers(2023) Ozoani, J.; Volkov, Y.; Волков, Юрий НиколаевичMargin adoption in a nuclear power plant (NPP) design is a frequent approach to strengthen the design’s robustness and provide an efficient way to handle uncertainties. However, the current trend of increasing fuel enrichment, including the use of MOX fuel to achieve a higher burnup, leads to non-uniformity in the energy release (power peaking factor) at the level of the fuel rod lattice, thereby causing a great effect on the reactor margins. One of the ways to reduce the power peaking factor is the use of burnable absorbers (BAs) which helps to minimize the power peaking factor. This work aims at enhancing the efficiency of the MOX fuel cycle for VVER-1200 reactor by replacing the Gadolinium burnable absorber to Erbia burnable absorber.
- ПубликацияТолько метаданныеComprehensive analysis of ASTRA benchmark with MCU-HTR and Serpent codes(2024) Kruglikov, A. E.; Shchurovskaya, M. V.; Volkov, Yu. N.; Geraskin, N. I.; Кругликов, Антон Евгеньевич; Щуровская, Мария Владимировна; Волков, Юрий Николаевич; Гераскин, Николай Иванович
- ПубликацияТолько метаданныеVerification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility(2020) Zizin, M. N.; Boyarinov, V. E.; Nevinitsa, V. A.; Fomichenko, P. A.; Volkov, Y. N.; Kruglikov, A. E.; Волков, Юрий Николаевич; Кругликов, Антон ЕвгеньевичCoupled neutronic and thermal hydraulic calculation codes are verified for calculating the design of modern and prospective types of nuclear reactors. This verification is done by comparing experimental and calculated results for stationary and transient conditions. This paper presents ShIPR (Shell of Intelligent Package for Reactor) Integrated Development Environment with automatic generation of head programs based on the chain of computational modules. The aim of this study is to find the reason of a discrepancy in the modelling of sub-critical states that was found in previous work. The comparison of ShIPR stationary module with Monte-Carlo code (MCU) and experimental results on ASTRA HTGR critical facility was presented in the paper. To compare the detector readings and MCU calculation with the ShIPR module, the interpolation cross-section procedure was performed. This procedure allows simulating 235 U fission reaction rates (detector readings) in the complicate, annular core, using the micro-cross sections prepared by the cell-lattice code. We found that the calculation accuracy of stationary ShIPR module is on an acceptable level but the macro constants for control rods need to be prepared independently, given with surroundings.
- ПубликацияОткрытый доступNuclear education in Russia and abroad Ядерное образование в России и в зарубежных странах(2019) Volkov, Y. N.; Geraskin, N. I.; Kosilov, A. N.; Волков, Юрий Николаевич; Гераскин, Николай Иванович; Косилов, Андрей Николаевич© 2019 Moscow Polytechnic University. All rights reserved.The education of a future nuclear professional provides the basic competencies that will influence the performance of a future specialist throughout his or her future professional career. The article discusses the best practices and main trends in higher education that have developed in the field of nuclear technologies in Russia and abroad. The analysis is based on the materials prepared by various international organizations and professional communities, and the experience of the MEPhI. The article discusses such issues as interaction between state, nuclear industry and higher education institution; the quality of nuclear education (four basic principles of training nuclear specialists in MEPhI), the transition to two-tier system in nuclear education; the international cooperation in nuclear sphere; export of nuclear education; and vocational guidance for school students.
- ПубликацияТолько метаданныеDevelopment of Reduced 3D Models for Neutronic Calculations of the ASTRA Critical Facility(2022) Nevinitsa, V. A.; Fomichenko, P. A.; Boyarinov, V. F.; Zimin, A. A.; Kruglikov, A. E.; Volkov, Y. N.; Кругликов, Антон Евгеньевич; Волков, Юрий Николаевич
- ПубликацияОткрытый доступComputational analysis of experiments to determine the kinetic parameters at the ASTRA HTGR type critical facility(2020) Zizin, M. N.; Boyarinov, V. F.; Nevinitsa, V. A.; Fomichenko, P. A.; Kruglikov, A. E.; Volkov, Y. N.; Кругликов, Антон Евгеньевич; Волков, Юрий Николаевич© Published under licence by IOP Publishing Ltd.The zero power ASTRA critical facility is intended for experimental investigations of neutronic features of modular High Temperature Gas Cooled Reactors. The computational analysis of non-stationary experiments carried out at the ASTRA critical stand to determine the kinetic parameters is carried out using SHIPR diffusion program. To measure the kinetic parameters, the impulse Simmons-King method was used. The computational analysis were carried out for 4 different configurations of ASTRA critical stand. Since in case of nonstationary calculation by implementation of the spatial kinetics approximation, it is necessary to set the neutron group velocities the full-scale calculations of neutron spectra were carry oud using the MCU program in order to take into account the spectrum that is established in the full-scale reactor model. On the basis of a comparison of the experimental and calculated results, a conclusion was made about the applicability of the applied effective calculation models for neutronic calculations of HTGR-type reactors.
- ПубликацияТолько метаданныеAxial Distributions of Fission Reaction Rates in the Annular Core of the ASTRA Critical Facility with Poison Profiling Elements in the Internal Reflector(2021) Nevinitsa, V. A.; Boyarinov, V. F.; Fomichenko, P. A.; Zimin, A. A.; Volkov, Y. N.; Kruglikov, A. E.; Волков, Юрий Николаевич; Кругликов, Антон ЕвгеньевичComputational modeling of experiments on measurement of axial distributions of fission reaction rates in configurations of the ASTRA critical facility simulating a HTGR with annular core is performed. Absorbing elements were installed in the internal reflector of critical assemblies to flatten the neutron flux radial distribution. Measurements of the fission reaction rates were performed both in a configuration with a flattened neutron field and in a configuration with control rods (CR) inserted in an external graphite reflector.