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Лаборатория динамики ядерных реакторов (Кафедра №5 ИЯФиТ)

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Волков, Юрий Николаевич
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Homogenised group constants generation using Monte Carlo codes for diffusion calculation of pebble bed reactor
(2020) Nevinitsa, V. A.; Fomichenko, P. A.; Zizin, M. N.; Kruglikov, A. E.; Shchurovskaya, M. V.; Volkov, Yu. N.; Кругликов, Антон Евгеньевич; Щуровская, Мария Владимировна; Волков, Юрий Николаевич
© Published under licence by IOP Publishing Ltd.This study is focused on the development of homogenization technique for the ASTRA pebble bed critical facility. The methods of generating homogenized few-group cross sections using continuous energy Monte Carlo codes MCU-PTR and Serpent 2.1.29 for full core diffusion calculation of pebble bed reactor were studied. 13-group cross sections were used in the SHIPR diffusion code to calculate the simplified cores of the ASTRA critical facility with HTGR-type fuel and a graphite reflector. Cross-verification of Serpent and MCU-PTR applied to HTGR system was carried out. Different homogenization schemes were tested for the SHIPR model and compared against Monte Carlo solutions. Diffusion coefficients for the fuel calculated using out-scatter approximation and cumulative migration method (CMM) were compared. It was shown that diffusion coefficients for fuel of pebble bed reactor calculated by CMM may reduce the difference between the diffusion and Monte Carlo simulation. The abilities of Serpent and MCU-PTR for modelling pebble bed reactors were compared.
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Parallel calculation of the stationary diffusion equation
(2020) Zizin, M. N.; Soldatov, E. O.; Volkov, Yu. N.; Волков, Юрий Николаевич
© Published under licence by IOP Publishing Ltd.Considering the complex neutron-physical systems with the number of calculation points than 1 million, the calculation time can be an hour or more, and in case of non-stationary process with the small step of time, the waiting can be a month. The aim of the study is to develop effective techniques for the stationary computational modeling using parallelization technology to imply in non-stationary calculations. The parallelization scheme with height decomposition for stationary model was developed. The calculated speedup on the parallel part of the code are in good agreement with the linear dependence. The theoretical possible acceleration was derived using Amdal's law. Comparing the obtained and theoretical curves demonstrates that the developed parallelization scheme has less acceleration due to losses. The losses and their relative contribution were identified.
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Computational 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.
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Enhancing the efficiency of the MOX fuel cycle for VVER-1200 using burnable absorbers
(2023) Ozoani, J.; Volkov, Y.; Волков, Юрий Николаевич
Margin 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.
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Физические особенности режимов ускоренной утилизации оружейного плутония в реакторах типа ВВЭР
(НИЯУ МИФИ, 2015) Волков, Ю. Н.; Волков, Юрий Николаевич; Наумов, В. И.
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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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Направления исследований: -Параллельные вычисления на основе технологий MPI и OpenMP Повышение эффективности работы нестационарных модулей нейтронно-физического расчета. Используемое программное обеспечение - JULIA, FORTRAN - Комплексные нейтронно-физические и теплогидравлические расчеты Нейтронные процессы влияют на распределение тепла в реакторе, а тепловые условия могут изменять поведение нейтронов. Это создает необходимость в комплексном подходе к расчетам, где учитываются взаимосвязи между этими двумя областями. Для выполнения комплексных расчетов требуются мощное программное обеспечение и вычислительные ресурсы. Разработка и оптимизация таких программ могут быть трудоемкими и требовать значительных затрат. Используемое программное обеспечение – COMSOL, Serpent, MCU, MCNP - Анализ эффективности и безопасности перспективных реакторных систем В основном тема касается высокотемпературных реакторов, реакторных систем на сверхкритических параметрах, малых модульных реакторов
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