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Афанасьев, Валерий Викторович

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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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Афанасьев
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Валерий Викторович
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20202
11
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    Investigation of using U-233 in thorium base instead of conventional fuel in Russian PWR by SERPENT Code
    (2020) Abu, Sondos, M. A.; Hassan, A. A.; Alassaf, S. H.; Savander, V. I.; Afanasyev, V. V.; Савандер, Владимир Игоревич; Афанасьев, Валерий Викторович
    © Published under licence by IOP Publishing Ltd.In this work, the fuel assembly of type TVS-2006, which is used in Russian reactor VVER-1200, is considered. A proposed fuel of Thorium and Uranium-233 ((Th232+U233)O2 has been investigated to replace the fuel currently used (U238 as a fertile and U235 as fissile). This has been done in order to compare the; conversion ratio, reproduction factor (?), burnup, effective delayed neutrons fraction (ßeff), Minor Actinides (MA) inventory, and Temperature coefficients of reactivity. The calculations performed using the Monte Carlo code (SERPENT-2.31) to analyze and compare the two fuels. Results showed that using U-233 in the Thorium base will considerably increase the reactivity at the Beginning Of Cycle (BOC), increase the conversion ratio, and burn up. Besides, the safety parameters for the proposed Th-based fuel, in general, lower than that for Low Enriched Uranium (LEU) but still acceptable.
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    Modeling of Iter Equatorial Neutron Diagnostics Equipment
    (2020) Denden, O.; Afanas'ev, V. V.; Al-Amin, M.; Афанасьев, Валерий Викторович
    © 2020, Springer Science+Business Media, LLC, part of Springer Nature.In the course of a controllable thermonuclear fusion reaction the state of the plasma in the reactor must be monitored. Neutron diagnostics can provide some parameters of the plasma in the thermonuclear reactor. In the present work, the neutron diagnostics of the equatorial port of the ITER is checked by means of Monte Carlo modeling of seven external fast-neutron spectrometers based on solid stilbene scintillators distributed in the port with their collimators and the efficiency of the spectrometers is determined.