Персона: Пугачев, Павел Александрович
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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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- ПубликацияОткрытый доступDevelopment of a virtual analogue of uranium-graphite subcritical assembly and visualization of the neutron flux distribution in virtual reality(2020) Kiryukhin, P.; Shcherbakov, A.; Romanenko, V.; Pugachev, P.; Khomyakov, D.; Tikhomirov, G.; Zadeba, E.; Кирюхин, Павел Константинович; Щербаков, Александр Антонович; Романенко, Владислав Игоревич; Пугачев, Павел Александрович; Хомяков, Дмитрий Андреевич; Тихомиров, Георгий Валентинович; Задеба, Егор Александрович© 2020 The Authors. Published by Elsevier B.V.The article describes the new software product developed at MEPhI. It represents a virtual reality simulation of an experiment on a subcritical uranium-graphite assembly. This practical work plays an important role in the training of young specialists studying the physics of nuclear reactors. However not all students have access to real experimental facilities, this fact makes it necessary to complement real experiment with simulation in virtual reality that allows to accurately reproduce the actions that the student performs during the real practical work. This approach let to increase the efficiency of the educational process and even expand the capabilities of real experimental assembly by visualizing physical processes during its operation.
- ПубликацияОткрытый доступAnalysis of the methods for group constants generation for calculation of a large SFR core using Serpent 2 and CriMR codes(2020) Gerasimov, A. S.; Akpuluma, D. A.; Smirnov, A. D.; Pugachev, P. A.; Tikhomirov, G. V.; Смирнов, Антон Дмитриевич; Пугачев, Павел Александрович; Тихомиров, Георгий Валентинович© Published under licence by IOP Publishing Ltd.This work aimed at generating homogenized group constants using the Serpent code and then using the CriMR diffusion code to model the large SFR OECD 3600 MWth MOX core. The results were compared with a full core reference Monte Carlo solution by Serpent. Reactivity feedback parameters were also considered. Generating the group constants from separate fuel assemblies allows for simultaneously carrying out calculations and then using the results as input in diffusion codes rather than waiting so long for a 3D full core Monte Carlo calculation to be completed. From the results of the integral parameters we see a close agreement in the calculation codes. The differences can be attributed to the errors that could arise from generating the constants from individual sub-assemblies. The differences in the underlying physics and approximations used in development of the codes could also be a factor. Another way the errors could be reduced is by checking to see that the sub-assembly configurations used in the non-multiplying zones are as close as possible to the real layout in a full 3D core.
- ПубликацияОткрытый доступCORIUMSITY program code for the consequences analysis of a severe core melt accident(2020) Saldikov, I. S.; Bogdanova, E. V.; Pugachev, P. A.; Ryzhov, S. N.; Smirnov, A. D.; Ternovykh, M. Y.; Tikhomirov, G. V.; Богданова, Екатерина Владимировна; Пугачев, Павел Александрович; Рыжов, Сергей Николаевич; Смирнов, Антон Дмитриевич; Терновых, Михаил Юрьевич; Тихомиров, Георгий Валентинович© Published under licence by IOP Publishing Ltd.As part of the tasks to improve the nuclear safety of nuclear power plants, a new program code was developed. The CORIUMSITY program code developed, considered in this work, is intended to analyze the scenario in which an accident at a nuclear power plant is simulated with the melting of the core and the formation of the so-called "corium"- a mixture of nuclear and structural materials of the nuclear reactor core, formed as a result of thermal and mechanical impact during an accident. The CORIUMSITY program code, is intended to analyze several scenarios of different accidents, include an accident with reactor core melting. The functions of this code can help in solving many urgent nuclear safety problems. One of the main methods of operation of the CORIUMSITY code algorithms is the matrix exponential method, which consists in using a matrix function of a square matrix, in which as values are used indicators corresponding to nuclides from the CORIUMSITY code database. The program implements an iterative Euler method for solving the system of levels of nuclear fuel burnup. The CORIUMSITY code was verified with benchmark data to assess the accuracy of the calculation.
- ПубликацияТолько метаданныеVisualization of neutron characteristics distribution of debris particles(2020) Takezawa, H.; Muramoto, T.; Nishiyama, J.; Obara, T.; Pugachev, P. A.; Bogdanova, E. V.; Saldikov, I. S.; Smirnov, A. D.; Ternovykh, M. Y.; Tikhomirov, G. V.; Пугачев, Павел Александрович; Богданова, Екатерина Владимировна; Смирнов, Антон Дмитриевич; Терновых, Михаил Юрьевич; Тихомиров, Георгий Валентинович© 2020 National Research Nuclear University. All rights reserved.Accident at Fukushima Daiichi nuclear power plant led to increase of importance of safe-ty justification for processes at post-accident facilities in nuclear industry. One of such pro-cesses is extraction of corium from reactors cavity. Recriticality of this process is defined by potential unacceptable accident. This paper introduces supporting code for neutron fluxes and reaction rates visualization in systems with complex geometry that can be used in model-ing of corium removing works. Visualization code is based on Unreal Engine 4 game engine. Code allows observing neutronic functionals distribution in three dimensions. The reseach and provided implementation details help to understand the physical processes that take place as the accidents occur during corium removing works.
- ПубликацияОткрытый доступDevelopment of virtual analogues of nuclear facilities in virtual reality(2020) Dashanova, E. A.; Zadeba, E. A.; Kiryukhin, P. K.; Pugachev, P. A.; Romanenko, V. I.; Tikhomirov, G. V.; Khomyakov, D. A.; Shcherbakov, A. A.; Yushin, I. M.; Дашанова, Екатерина Александровна; Задеба, Егор Александрович; Кирюхин, Павел Константинович; Пугачев, Павел Александрович; Романенко, Владислав Игоревич; Тихомиров, Георгий Валентинович; Хомяков, Дмитрий Андреевич; Щербаков, Александр Антонович© Published under licence by IOP Publishing Ltd.Using virtual reality technology - a modern trend. The nuclear industry is no exception. This article provides an overview of mathematical models used to create virtual analogue of critical assembly Godiva in virtual reality. Godiva - there is a simple example that allows to hone techniques for creating more complex virtual analogues of nuclear reactors and nuclear facilities. Mathematical models include stationary and dynamic ones. The stationary model is based on data from calculations carried out using Monte Carlo programs such as MCU, Serpent and Geant4. An approach is also described that makes it possible to calculate the reverse multiplication from the values of the effective multiplication factor for various states of the subcritical assembly. The dynamic model allows one to calculate the neutron-physical characteristics of the supercritical assembly during fast processes such as a neutron burst. In conclusion, there are other examples of virtual analogs created using similar approaches.
- ПубликацияОткрытый доступNeutronic modeling of a subcritical system with corium particles and water (from international benchmark)(2020) Smirnov, A. D.; Bogdanova, E. V.; Pugachev, P. A.; Saldikov, I. S.; Ternovykh, M. Y.; Tikhomirov, G. V.; Смирнов, Антон Дмитриевич; Богданова, Екатерина Владимировна; Пугачев, Павел Александрович; Терновых, Михаил Юрьевич; Тихомиров, Георгий Валентинович; Obara, T.; Nishiyama, J.; Muramoto, T.; Takezawa, H.