Персона: 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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Валерий Викторович
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- ПубликацияТолько метаданныеAnalysis of Libraries of Evaluated Nuclear Data Using the Example of Calculations of Np-237 Sphere Criticality(2024) Khassan, A. A.; Dikova,T. S.; Afanasyev, V. V.; Афанасьев, Валерий Викторович
- ПубликацияОткрытый доступInvestigation 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.
- ПубликацияТолько метаданныеModeling 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.
- ПубликацияТолько метаданныеStudy of silicon photomultipliers (SiPM) with organic scintillator for neutron diagnostics of thermonuclear plasma(2022) Boukerdja, L.; Dendene, O.; Afanasiev, V. V.; Lushin, S. V.; Chergui, A. C.; Stifutkin, A. A.; Афанасьев, Валерий Викторович; Стифуткин, Алексей Анатольевич© 2022 Elsevier B.V.The spectrometry of neutrons produced by fusion reactions of plasmatic ions is the most powerful neutron diagnostic tool for monitoring reactor operating power, temperature and concentration of ions. Currently, new generations of silicon photomultipliers (SiPMs) are being used in several light detection fields, including nuclear domain; they have performances similar to conventional photomultipliers tubes (PMTs), while benefiting advantages of solid-state technology such as insensitivity to magnetic and electric fields, excellent temperature stability, robustness, low operating voltage, small size, and low cost. Consequently, they could be a useful device in neutron spectrometer based on recoil proton method for neutron diagnostics of hot plasmas. In this paper, we have demonstrated SiPMs capabilities to be used for fast neutron detection as well as their dynamic range for thermonuclear fusion neutron spectrometry (14 Mev). The responses of SiPMs having different sizes of active areas and microcells manufactured by Ketek and SensL have been studied. Excellent pulse shape discrimination of PuBe source radiations by SiPMs combined with a stilbene crystal has been proven; the figure of merit has reached 3.33. The study has also allowed the determination of the size parameters of SiPMs that are suitable for neutron diagnostics of thermonuclear plasmas.
- ПубликацияТолько метаданныеOptimization of the cold moderator for the new pulsed reactor NEPTUN(2023) Hassan, A. A.; Bulavin, M. V.; Afanasyev, V. V.; Афанасьев, Валерий ВикторовичThe Frank Laboratory of Neutron Physics (FLNP) at the Joint Institute for Nuclear Research (JINR) has begun designing a new research reactor, NEPTUN, to replace the IBR-2M (pulsed fast reactor - the name in russian) reactor, which is expected to be out of service between 2032 and 2036. The IBR-2 reactor is a third-generation neutron source that started working in 1982 at Dubna, Russian Federation. The IBR-2M reactor was successfully modernized in 2012. The NEPTUN reactor is a fourth-generation neutron source that will use Np-237 as a nuclear fuel for the first time. It was studied if mesitylene (1,3,5-trimethylbenzene), which is now being utilized effectively in the reactor IBR-2M, might be used as a cold moderator in the new research reactor NEPTUN with an average thermal power of 15 MWt. A study of five materials used as a cold neutron moderator at various temperatures was also conducted. Longer working times for cold moderator material were another goal of optimization. According to the findings, mesitylene at a temperature of 20 K should be used as a cold moderator to get the greatest neutron flux at a wavelength of 3 ≤ λ ≤ 10 Å. Additionally, ortho hydrogen at 20 K could increases the cold neutron flux with wavelengths, λ ˃ 10 Å.
- ПубликацияТолько метаданныеOptimization of the Thermal Moderator for a New Pulsed Reactor NEPTUN(2023) Hassan, A. A.; Bulavin, M. V.; Afanasyev, V. V.; Podlesnyy, M. M.; Афанасьев, Валерий Викторович