Персона: Зимин, Вячеслав 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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Вячеслав Геннадьевич
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- ПубликацияТолько метаданныеSKETCH-N/ATHLET steady-state and dynamic coupling scheme verification on Kalinin-3 benchmark results(2020) Zimin, V. ; Nikonov, S. ; Perin, Ya. ; Henry, R. ; Velkov, K. ; Романенко, Владислав Игоревич; Тихомиров, Георгий Валентинович; Tikhomirov, G. V.; Romanenko,V. I.; Зимин, Вячеслав ГеннадьевичThe paper describes the multi-physics coupling scheme between the SKETCH-N nodal neutronics code and the best-estimate thermohydraulic code ATHLET v3.2. Some first results are discussed. Various possible options of coupling have been considered. A scheme is selected and applied for data exchange between the codes based on MPI library. The verification and validation were performed using the transient of the Kalinin-3 international Benchmark. The simulation results show good agreement with experimental data and calculations performed by the participants of the benchmark. Parallel to the coupling scheme development, a visualization system to process the results is being created. The steady-state analysis is carried out using both simple and complex thermohydraulic models. The calculations of the transient \Switch off of one MCP (Main Coolant Pump) at nominal power" is performed applying a more elaborate thermohydraulic model taking into account inter- channel mass transfer.
- ПубликацияТолько метаданныеAnalysis of the Kalinin-3 coolant transient benchmark by SKETCH-N/SKAZKA code system(2020) Ojinnaka, C. A. S.; Zimin, V. G.; Strashnykh, V. P.; Nikonov, S. P.; Зимин, Вячеслав Геннадьевич; Страшных, Вадим Петрович© 2020 Elsevier LtdThe switching off of the one of four main circulation pumps results in the Kalinin-3 Coolant Transient Benchmark. The benchmark contains four exercises, but this article shows the results of the exercise two of the VVER-1000 reactor core calculation. Reactor core analysis code SKETCH-N/SKAZKA is used to simulate the steady-state and transient conditions of the VVER reactor. The reactor core boundary conditions for the problem are provided by ATHLET/BIPR-VVER code. In the initial steady-state condition and at the end of the transient the power distribution is compared with the nuclear power plant (NPP) data. The average error in 3-D power distribution is 3.6%. The average difference in fuel assembly (FA) power is less than 2%. In the transient calculation, we compared with the experimental data the reactor power and axial offset. There is close agreement between the numerical results and NPP data.
- ПубликацияТолько метаданныеEstimation of the Pure Condensate Flow Rate in the Starting Range in the Startup to the Minimum Controlled Power Level after the Activation of Emergency Protection(2022) Al-Shamayleh, A. I.; Solovyov, D. A.; Semenov, A. A.; Shchukin, N. V.; Zimin, V. G.; Potapov, V. S.; Соловьев, Денис Алексеевич; Семенов, Андрей Артемьевич; Щукин, Николай Васильевич; Зимин, Вячеслав Геннадьевич
- ПубликацияТолько метаданныеSelecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel(2023) Tanash, H. A.; Solovyov, D. A.; Zimin, V. G.; Lobarev, A. L.; Plotnikov, D. A.; Schukin, N. V.; Соловьев, Денис Алексеевич; Зимин, Вячеслав Геннадьевич; Щукин, Николай Васильевич