Научные журналы НИЯУ МИФИ

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3D Model of the Winding Product
(НИЯУ МИФИ, 2024) Tomilova, O. V.; Rokotov, N. V.
The article presents the results of computer modeling of a winding product. It describes the method for creating a 3D model based on a series of flat sections passing through the axis of the package. The issues encountered during 3D modeling and their solutions are discussed. The authors propose using the continued fraction method to describe the structure of winding products and optimize the model for subsequent calculations in CAE programs. The article provides information about the process of creating a 3D model of the winding product, as well as the possibilities for reducing computational resources required for modeling. The results of computer modeling of various winding types are presented. In the conclusion, the authors assert that the developed method for analyzing and synthesizing the structure of precision winding using the continued fraction approach allows for the exploration of various winding types and the creation of optimal 3D models that replicate their structure. These models can be used for further research and as digital models of winding products.
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3D Visualization of Asynchronous Many-Task Scheduling Algorithm
(НИЯУ МИФИ, 2023) Vasev, P. A.
The paper is devoted to the issue of visualization of the algorithm for scheduling parallel tasks. Task scheduling is a key part of the online visualization and parallel programming environment developed by the author. When programming a parallel version of one mathematical application, a suspicion arose that the scheduling algorithm does not optimally distribute the load between the workers. In this connection, it was decided to visualize its work in order to see the overall picture and possible problem areas of the algorithm. The constructed view successfully coped with the problem, and the scheduling algorithm was improved.
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3D-Cloning of Core Plug Structures: Insights and Challenges into FDM and DLP Printing Based on Microtomography Data.
(2025) Kadyrov, R. I.; Nguyen, T. H.; Statsenko, E. O.; Kharin, N. V.
This study explores the use of FDM (Fused Deposition Modeling) and DLP (Digital Light Processing) 3D printing techniques to create accurate replicas of core plugs from reservoir rock structures based on µCT (microtomography) scans. Due to the challenges in obtaining core plug samples for reservoir characterization, this research aims to develop a cost-effective and reusable alternative by replicating the pore structure of natural rocks for use in experimental studies. A carbonate core plug was µCT-scanned to obtain a high-resolution 3D digital model of its pore structure, which was then digitally processed to simplify its complex pore geometry for 3D printing. The model was printed using FDM with 0.2 mm and 0.4 mm nozzles, as well as DLP techniques. Both methods were evaluated by re-scanning the printed samples with µCT and analyzing their structural, porosity, and permeability characteristics. FDM printing demonstrated the ability to replicate larger pore structures, but the presence of interlayer gaps resulted in inflated porosity and permeability values compared to the original core plug, and fine pore features were inconsistently replicated across multiple prints. DLP printing, while more accurate in capturing morphology and finer details, also exhibited variability in the reproduction of small pore elements. Furthermore, cracks were observed in DLP samples due to stresses during resin curing, and the retention of residual resin in pores affected permeability and reduced effective porosity. The study highlights the limitations of both FDM and DLP methods in fully reproducing the complexity of pore networks, particularly at fine scales. The results point to the need for technological improvements in both methods to enhance the accuracy and reproducibility of 3D-printed core replicas.
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3D-печатные иерархические решётчатые метаматериалы: интеграция механической прочности и ультразвуковой чувствительности для биомедицинских применений
(2025) Шишковский, И. В.
Представлено комплексное исследование акустических свойств иерархических 3D-печатных метаматериалов из полилактида, разрабатываемых для применения в тканевой инженерии. Численное конечно-элементное моделирование проведено для изучения распространения ультразвуковых волн в диапазоне 1–9 МГц сквозь решётчатые структуры типа октаэдр, соты или алмаз. Рассмотрено влияние геометрической топологии и эффективных физических параметров (модуля Юнга, плотности, скорости звука) на распределение акустического давления. Показано, что изученные типы трижды периодических структур с минимальной поверхностью демонстрируют уникальные паттерны локализации и рассеяния энергии ультразвукового поля, что открывает возможности для использования таких структур в качестве скаффолдов или при контролируемом высвобождении лекарств с диагностической функцией. Полученные результаты позволяют прогнозировать взаимодействие пористых решётчатых метаматериалов с ультразвуком и оптимизировать их применение в динамике с помощью неинвазивной ультразвуковой диагностики.
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45 лет Самарскому филиалу ФИАН
(2025) Азязов, В. Н.; Майорова, А. М.
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70 лет ДУРАКОВСКОМУ АНАТОЛИЮ ПЕТРОВИЧУ, заместителю главного редактора БИТ, доценту НИЯУ МИФИ, кандидату технических наук
(НИЯУ МИФИ, 2024)
Дорогой Анатолий Петрович! Редакционный Совет и Редакционная Коллегия журнала Безопасность Информационных Технологий, все авторы и читатели нашего журнала от души поздравляют Вас с юбилейным Днем рождения! В качестве заместителя главного редактора Вы являетесь душой редколлегии нашего журнала. При этом у Вас множество других обязанностей: директор Аттестационно-испытательного центра информационной безопасности и систем защиты информации НИЯУ МИФИ, заместитель руководителя Органа по аттестации объектов информатизации по требованиям безопасности информации, руководитель испытательной лаборатории по сертификации средств защиты информации от несанкционированного доступа, аккредитованных ФСТЭК России, а также член УМО по направлению информационная безопасность, постоянный член ТК 362 по стандартизации «Защита информации». Более 10 лет Вы являетесь одним из лидеров кафедры «Стратегические информационные исследования» НИЯУ МИФИ. Вами опубликовано свыше 70 научных трудов, получено более 10 патентов на изобретения, свидетельств на «ноу-хау» и программ для ЭВМ. Под Вашим руководством разработано свыше 15 учебных программ дополнительного профессионального образования в области информационной безопасности, согласованных с ФСТЭК России и ФСБ России, по которым ведется подготовка в НИЯУ МИФИ работников организаций-лицензиатов ФСТЭК России и ФСБ России, изданы 4 учебных пособия, которые приказом ФСТЭК России утверждены в качестве документов национального уровня. Ваш профессионализм знают и уважают все Ваши соратники. При этом Вы являетесь заядлым и удачливым рыбаком, одним из основателей альпклуба МИФИ, участником спасательных работ Спита́кского землетрясения 1988 г. Вы имеете множество государственных и ведомственных наград, но остаетесь скромным и доброжелательным товарищем по отношению ко всем своим коллегам, независимо от их чинов и званий. Сердечно поздравляем Вас, дорогой Анатолий Петрович, со знаменательной датой и желаем крепкого здоровья, дальнейших успехов и удачи во всем! С искренним уважением, Редакционная коллегия журнала «БИТ»
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70 лет ШЕЛУПАНОВУ АЛЕКСАНДРУ АЛЕКСАНДРОВИЧУ, президенту ТУСУР, доктору технических наук, профессору
(НИЯУ МИФИ, 2024)
Дорогой Александр Александрович! Поздравляем Вас с 70-летним юбилеем и благодарим за огромный вклад в отечественную науку и высшую школу! Ваше имя широко известно благодаря выдающимся достижениям в области информационных технологий и кибернетики – более 500 публикаций, в том числе 15 научных монографий, 50 учебников, учебных и учебно-методических пособий, 50 патентов на изобретения и свидетельствах о государственной регистрации программ для ЭВМ. Ваши работы, такие как «Основы информационной безопасности», «Технические средства и методы защиты информации», «Системный анализ в защите информации» стали основой для разработки передовых методов защиты данных и подготовки тысяч специалистов по информационной безопасности! Как президент и в недавнем прошлом ректор ТУСУРа, как директор Центра компетенций национальной технологической инициативы «Технологии доверенного взаимодействия» ТУСУРа», Вы воспитали множество талантливых учёных и инженеров в области защиты информации – под Вашим научным руководством защищено 4 докторских и 30 кандидатских диссертаций. За годы Вашей карьеры Вы были отмечены множеством наград, включая звание заслуженного работника высшей школы РФ, лауреата премии Правительства РФ в области образования и дважды лауреата премии Правительства РФ в области науки и техники. Желаем Вам крепкого сибирского здоровья, творческого долголетия и радости от общения с близкими. Пусть каждый день приносит новые открытия, удовлетворение и позитивные эмоции. Всегда ждем Ваших публикаций на страницах журнала БИТ. С искренним уважением, Редакционная коллегия журнала «БИТ»
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A brief investigation of the dose field virtual simulation tools for reactor decommissioning and preliminary design for the HWRR reactor in China
(2024) Guo, Y.; Nie, P,; Li, R.; Zhang, L.; Zhang, X.; Ren, R.; Zhao, Z.
The calculation and visualization of the dose field in the decommissioning of nuclear facilities is one of the important functions of the decommissioning virtual simulation system. The dose field simulation tools can provide radiation field distribution and play an important role in determining the decommissioning plan and protecting personnel during the engineering implementation process. This article investigates the development of dose field calculation and visualization in the reactor decommissioning virtual simulation systems. A preliminary technology plan suitable for the development of the decommissioning dose field calculation and visualization display programs of the first Heavy Water Research Reactor (HWRR) in China is proposed. The applicability of the selected scheme is analyzed. The functional requirement and development direction of the HWRR reactor decommissioning dose field tool are preliminarily determined. Furthermore, the reactor vessel of HWRR reactor is modeled, the dose field distribution is calculated and visualized based on the preliminary decommissioning code. This research can provide technical support for the development of the decommissioning simulation system for the first HWRR reactor in China.
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A computer code for optimizing the neutronics model parameters based on results of reactor physics experiments
(2023) Andrianov, A. A.; Andrianova, O. N.; Korovin, Y. A.; Kuptsov, I. S.; Spiridonova, A. A.
The paper describes in brief the functional capabilities of a computer code for optimizing the neutronics model parameters (neutron data, technological parameters, and their covariance matrices) based on results of reactor physics experiments using conditional nonlinear multi-parameter optimization algorithms. The code’s application scope includes adjustment of neutron constants, technological parameters and their covariance matrices based on integral measurement results, formulation of requiremen117198ts with respect to the neutron data uncertainties for achieving the target accuracies in calculation of the reactor functionals, and estimation of the reactor performance prediction accuracy, as well as the informativity and similarity metrics of reactor physics experiments with respect to each other and in relation to the target reactor system. The paper also considers some examples of using the code to refine the neutronics models of nuclear reactor and fuel cycle systems based on results of reactor physics experiments.
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A High-Level Adaptation Toolkit for Unified Integration of Software Systems with Neural Interfaces
(НИЯУ МИФИ, 2024) Chuprina, S. I.; Labutin, I. A.
The paper is devoted to the urgent problem of automating the process of integrating different types of neurointerfaces into the infrastructure of the Internet of Things. Due to the low-level nature of these devices and related tools, integrating neurointerfaces with a wide range of IoT devices is a complex task requiring specialized knowledge and skills in the fields of neuroscience and signal processing. To tackle the significant challenge of automating such kind integration we continue to improve our previously proposed ontology-driven methods and tools for seamless integration of software systems with neural interfaces in a unified way. The presented notable improvements include the introduction of a new data processing pipeline that utilizes a portable device to validate the effectiveness of the system and the development of an intuitive graphical user interface enabling real-time data visualization facilities that provides an easy and understandable feedback.
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A spatial dynamic model of the SHELF-M reactor facility with fuel and coolant temperature feedbacks
(2023) Plotnikov, D. A. ; Lobarev, A. L.; Krivoshein, I. N.; Kuznetsov, P. B. ; Ivanyuta, A. N.
The evolution of nuclear power is inseparably linked with the development of breakthrough solutions in the field of economic development of new territories. A pressing issue in this connection nowadays is generation of power for remote and hard-to-reach areas with decentralized power supply. To resolve this issue, JSC NIKIET is developing a version of the SHELF-M modular water-cooled water-moderated reactor facility as a source of power for offshore installations, including the Arctic coast areas, as well as localities with practically no power and transport infrastructure. One of the stages in justifying the safety of the reactor facility operation is to investigate the behavior of the reactor facility in dynamic transient modes at various power levels. To this end, a spatial dynamic model has been developed for the reactor facility with fuel and coolant temperature feedbacks. The dynamic model development process is a complex task that includes both preparation of constants for subsequent calculations and generation of the reactor neutronic and thermophysical models. The paper describes the development stages of the SHELF-M reactor facility spatial dynamic model and the results of coupled neutronic and thermophysical calculations for transients using the developed dynamic model of the reactor. Shim rod movement in the cold and hot states of the SHELF-M reactor facility is considered as transients.
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About definition and practical application of probabilistic safety indicators related to large accidental release
(2024) Lyubarskiy, A. V.; Tokmachev, G. V.; Mikhalev, A. V.; Kuzmina, I. B.
The probability of a large early release is one of the safety indicators that reflects the risk of fatalities during an accident at a nuclear power plant. Despite the fact that this indicator is very important, it is not defined in the federal rules and regulations of the Russian Federation. The article analyzes the worldwide experience related to determining criteria for large early release taking into account the statistical data of the specific country under consideration. Based on the analysis, the definition of a large early accidental release and the criteria for its achievement are formulated taking into account measures to protect the population living within the protective action planning zone (PAPZ), and an approach for their definition is proposed. A conclusion has been made about the sustainable nature of the goals identified using the NRC approach. A critical analysis of the safety indicators established worldwide allowed for the conclusion that it is necessary to improve the methodology for assessing the safety goals taking into account the specifics of NPP design, regional characteristics, phases of accident progression and other factors. The paper outlines the proposed approaches to determining high-level safety goals based on probabilistic targets – quantitative values for probabilistic health objectives (PHO) designated as PHO1 and PHO2 for the Russian Federation. A definition of a “large early release” is formulated and criteria for its achievement are proposed taking into account measures to protect the population living within the PAPZ. Thus, when assessing the degree, to which these goals are achieved in practice, it is proposed to take into account not only the likelihood of a large release during an accident at a nuclear power plant, but also measures aimed at protecting the population, in particular, evacuation. In this case, early deaths occur only when the population is not evacuated before the critical health dose loads from the release are reached.
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Actual problems of modeling thermal-hydraulic processes in fast neutron reactors
(НИЯУ МИФИ, 2024) Kuzina, Yu. A.; Sorokin, A. P.
The results of studies on hydrodynamics and heat transfer processes in fast neutron reactors are presented. Data on turbulent momentum transfer in rod bundles are analyzed. It is shown that the intensification of turbulent momentum transfer in the rod bundle channels is due to large-scale turbulent momentum transfer (secondary currents). The intensification of interchannel turbulent exchange in close-packed lattices of rods is explained. A dependence is obtained for the dissimilarity coefficients of interchannel convective exchange forced by wire wrapping in bundles of rods. The methods and results of numerical modeling of thermal hydraulics using the Monte Carlo method, thermomechanical analysis of the temperature field in fuel rod assemblies in the lifetime process are presented. The results of modeling based on a water model of temperature fields and the structure of coolant movement in the primary circuit of the reactor in various regimes are presented. A stable temperature stratification of the coolant was revealed in the peripheral zone of the upper chamber of the reactor above the side screens. It is shown that the process of boiling liquid metals in fuel assemblies has a complex structure, characterized by stable and pulsating regimes and a heat transfer crisis. The agreement between the results of experimental and numerical modeling is shown. A cartogram of the flow regimes of a two-phase flow of liquid metals in fuel rod assemblies has been plotted. The influence of the surface roughness of fuel elements on the boiling process and heat transfer during boiling of liquid metals is analyzed. Long-term cooling of a fuel assembly with a “sodium cavity” above the reactor core in accident regimes with boiling of liquid metals is shown. The objectives of further research are formulated.
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Adaptation of the Gauss-Newton Optimization Algorithm in Hilbert Diagnostics Using the Bunsen Flame as an Example
(НИЯУ МИФИ, 2024) Arbuzov, E. V.; Dubnishchev, Yu. N.; Zolotukhina, O. S.
The possibility of using the Gauss-Newton optimization algorithm in Hilbert diagnostics of reacting media (flames) is considered in the paper using the example of data on the temperature and main compounds of a laminar methane-air Bunsen flame. The method of reconstructing phase optical density fields is used to solve the inverse problem of Hilbert optics (it was previously proposed and tested on numerical models): the hilbertogram is calculated in the considered flame axisymmetric section, from which the initial values of the phase function and the medium refractive index are reconstructed. The applications scope expansion of the obtained results in the experimental data processing will be the work development.
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Additive Manufacturing of Personalized Brain-Computer Interface Headsets Reinforced by Scientific Visualization
(НИЯУ МИФИ, 2024) Chiruhin, D. A.; Ryabinin, K. V.
Recently, a large attention has been attracted to the brain-computer human-machine interfaces (BCI) based on electroencephalography (EEG). This emerging technology allows touchless control over digital systems, in which the commands are based on human brain activity. In the ideal case, it means controlling the systems virtually by thoughts, but in reality, also simpler approaches are highly demanded like reacting to concentration, relaxation, or specific emotions. Modern BCIs are based on detecting so-called brain waves, the electromagnetic field oscillations induced by brain neurons. These waves are captured by electrodes either intruded into the brain or placed on top of the head. Obviously, placing electrodes on the head is more demanded for non-medical applications of BCI because it is absolutely harmless for the person. To achieve this, special headsets are needed which can be put on the head like a helmet and ensure the correct positions for the electrodes mounted on them. In this regard, wearing comfort and anatomical accuracy of headsets play an important role in ensuring both ergonomics and precision of BCI. This paper focuses on automation of the personalized EEG headset manufacturing for BCI. The technological chain is proposed and corresponding software tools are developed to foster the complete cycle of BCI headset production for a particular person. The production steps include 3D scanning of the head, interactive editing of the electrodes’ location system, and automatic generation of a collapsible head cap model with sockets for EEG electrodes optimized for 3D printing. The performance of the pipeline has been validated in practice. The accuracy of electrodes’ placement has been evaluated by comparison with the head cap from professional medical equipment and is established as sufficient for BCI. The headset model editing and customizing tools are powered with scientific visualization and cognitive graphics techniques to be friendly for a wide range of users including those with no dedicated IT skills.
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Advanced development of nuclear power as a factor in ensuring sustainable development of humanity
(2024) Podchufarov, A. Y.; Galkina, A. N.; Vanina, S. S.
The future of nuclear power has been widely discussed by the scientific community and the public, which is explained by the high potential of peaceful nuclear technologies in providing mankind with affordable energy, preserving the climate, developing industry, medicine, science, and education. The materials of the study are devoted to assessing the impact of nuclear power on modern challenges and achieving indicators that are reflected in the Sustainable Development Goals. The paper uses the provisions of the intersystem interaction theory, system models for managing basic target indicators, methods of correlation, regression, autoregression analysis. The study confirmed the positive impact of nuclear power on the integral indicators of sustainable development. Considering the resource constraints, the preferred scenario for nuclear power development was substantiated, and its impact on achieving the integral indicators of the Sustainable Development Goals was assessed.
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An analysis of the “Fast” noise measurements of the dynamic VVER processes
(2024) Arkadov, G. V.; Pavelko, V. I.; Slepov, M. T.
Studies of maneuverable modes of VVER to confirm the possibility of participation of nuclear power plants in the mode of daily carrying capacity have been conducted for quite a long time. Tests at various nuclear power plants with VVER-1000 (Zaporizhzhia NPP in 1998, Khmelnitsky NPP in 2005, Tianwan NPP in 2007) have shown the practical possibility of NPP participation in the daily schedule of carrying capacity, however, the commissioning of nuclear power plants with VVER-1200 requires similar work on all new units with VVER-1200: NVAES-2, LNPP-2 Belarusian NPP. The article presents some aspects of the use of noise control methods for analyzing the condition of equipment and the core. Since the emergence of the technology of noise analysis of signals from VVER reactor installations, researchers have formulated several criteria for obtaining results of appropriate quality. The fundamental requirement for conducting noise experiments was the registration of data in stationary modes of operation of power units, since any non-stationarity made significant changes in spectral estimates, which ultimately complicated the work and “distorted” the results obtained. This requirement was included in the operating instructions of various diagnostic systems using noise signal analysis methods (the SUS system, manufactured by Siemens). For a long period of time, the current situation suited both developers of various diagnostic systems and NPP personnel operating them at power units. On the one hand, this was due to the imperfection of the technical means used (low speed of analog-to-digital converters, limited storage capacity, bulky equipment, etc.), on the other hand, the use of domestic NPP power units only in the base load mode without tracking daily power fluctuations in the power system. The standard archives of the upper block level system, the in-reactor control system and additionally produced multi-channel “fast” measurements with a frequency of 1 kHz for the analysis of maneuverable mode 95-55-95% of the VVER-1200 reactor plant were analyzed. Global disturbances of the core have been detected after one step of the regulatory body of the control and protection system, which attenuates within one second if the next step of the control and protection system has not occurred during this time. Such fast neutron processes can be controlled only by neutron-noise measurements with an upper frequency of at least 20 Hz.
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An Approach to Developing Data Visualization Tools Based on Domain Specific Modeling
(НИЯУ МИФИ, 2024) Dzheiranian, A. D.; Ermakov, I. D.; Proskuryakov, K. A.; Lyadova, L. N.
An approach to the development of data visualization tools is described that provides the ability to customize to the needs of users and the specifics of the domains in which they work, based on domain-specific modeling. The results of the analysis of data visualization tools and the possibility of customizing them to subject area based on the needs of users and the tasks they solve are briefly presented. It is shown that existing tools require programming skills from users to customize the data visualization format or to develop new visualization models. It is proposed to use domain-specific modeling tools (language toolkits) to create domain-specific languages (DSL) designed to develop new data visualization models that reflect the specifics of the tasks solved by users. The use of the developed tools does not require users to have professional knowledge of programming languages. The architecture of a knowledge-driven software system is described. The core of the system is a multifaceted ontology, which includes descriptions of languages and domains, as well as rules for generating new languages and transforming constructed models. Languages are designed to describe different classes of diagrams. The system includes tools for automating the creation of new DSLs by mapping the domain ontology onto the metamodel of the base language according to user-specified rules, which are also stored in the ontology. The classification of different types of diagrams forms the basis for creating an ontology of data visualization languages. An example of a basic language for creating diagrams is described. The ability to customize the DSL and transform visualization models developed with its help and generate code that implements the model is demonstrated. It is shown how interactive visualization can be created on the basis of the developed metamodels, extending the possibilities of visualizing large structured data.
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Analysis of Open Well Datasets
(НИЯУ МИФИ, 2024) Makienko, D. O.; Safonov, I. V.; Сафонов, Илья Владимирович
Recently, the number of studies devoted to the use of machine learning methods in geophysics has been increasing significantly. Examples of such investigations include the prediction of rock properties and separation of rock types according to quantitative characteristics. Annotated datasets are required to build and evaluate the quality of machine learning based models. This paper analyzes open labeled well datasets and related research. We consider data containing well logs, rock images, laboratory results, labeled zonation by lithotypes. Methods for visualizing well data are presented. We provide recommendations for oil and gas companies on the preferable format for making well data publicly available
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Analysis of radwaste accumulation in various scenarios of NP development
(2024) Kashirsky, A. A.; Solomatin, V. M.; Panov, S. A.; Rodina, E. A.; Egorov, A. V.; Dmitriev, S. A.; Shulga, A. Y.
Within the framework of “Proryv” project a radiation-equivalent approach to radioactive waste management is being envisioned with U and Pu recycling and MA transmutation. Successful industry-wide implementation of the design approaches should be planned in order to avoid considerable financial and radiological encumbrances caused by the NFC final stage for two-component nuclear power system (NPS) under formation on the basis of thermal and fast reactors. In order to ensure a successful industry-wide implementation of the approaches being developed, the back-end of the NFC should not constitute considerable a financial and radiological burden for the emerging two-component nuclear power system (NPS). This article addresses the problems concerning justification of radiological and technical-and-economic feasibility of MA partitioning and subsequent transmutation in FNR. The extent of MA accumulation as a result of TNR SNF reprocessing confirms the need for the introduction of MA partitioning technologies not only at all reprocessing plants planned for commissioning, but also at the plants now in operation. Based on available data, the study has shown that the implementation of the closed NFC with FNR contributes to significant reduction in the cost of disposal of radwaste compared to the scenario based exclusively on the development of VVER and open fuel cycle technologies. Recycling plutonium in fast reactors should be implemented in conjunction with MA to address environmental, non-proliferation and economic concerns of the back-end of advanced NFC. Within the scale of the future nuclear power system in Russia, an option such as this can only be realized on the basis of developing a FNR fleet.