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Перегляд Вопросы атомной науки и техники, 2017, № 2 за темою "Проблемы современной ядерной энергетики"

Репозиторій DSpace/Manakin

Перегляд Вопросы атомной науки и техники, 2017, № 2 за темою "Проблемы современной ядерной энергетики"

Сортувати за: Порядок: Результатів:

  • An autonomous system of a spent fuel pool cooling in WWER-1000 
    Ihschenko, O.P. (Вопросы атомной науки и техники, 2017)
    The issue of WWER-1000 spent fuel pool cooling in total blackout conditions is evaluated. A model of a spent fuel pool for MELCOR computer code is developed. Basic information about a spent fuel pool construction is shown. ...
  • Compton detector of neutrons for the energy yieldcontrol in the active zone of WWER 
    Shilyaev, B.A.; Ulybkin, A.L.; Rybka, A.V.; Kovtun, K.V.; Kutny, V.E.; Pudov, A.O.; Kutny, K.V. (Вопросы атомной науки и техники, 2017)
    The article examines the processes of radiative neutron capture by nuclei of atoms of metallic rhodium and hafnium. Rhodium is used as the emitter in the direct charge detectors of neutrons, which are used to control the ...
  • Contribution of radionuclides to heat release in the process of SNF dry storage 
    Rudychev, V.G.; Azarenkov, M.O.; Girka, I.O.; Rudychev, Y.V.; Shchus, O.P. (Вопросы атомной науки и техники, 2017)
    In the paper the radionuclide contribution to heat release at dry storage of spent nuclear fuel (SNF) of WWER-1000 was researched. β- and γ-radiation from 60 of the most active fission products, and α-radiation from 20 ...
  • Development of thermohydraulic models of core elements of “Neutron source” 
    Kukhotsky, O.V.; Nosovsky, A.V.; Dybach, O.M. (Вопросы атомной науки и техники, 2017)
    This article focuses on the development of independent thermohydraulic models of the core elements of the research nuclear subcritical facility. Its design and construction is currently being implemented by the National ...
  • Dispersion fuel for nuclear research facilities 
    Kushtym, А.V.; Belash, M.M.; Zigunov, V.V.; Slabospitska, O.O.; Zuyok, V.A. (Вопросы атомной науки и техники, 2017)
    Designs and process flow sheets for production of nuclear fuel rod elements and assemblies TVS-ХD with disper-sion composition UO₂+Al are presented. The results of fuel rod thermal calculation applied to Kharkiv subcritical ...
  • Expirience of using the SCALE software package for substantiation of nuclear safety of dry storage of spent nuclear fuel 
    Chernitskiy, S.V.; Soldatov, S.A. (Вопросы атомной науки и техники, 2017)
    SCALE software package has been used to model a ventilated concrete container for the dry storage of spent nuclear fuel. The methodology of calculations, which isused to substantiate the nuclear safety of dry storage, is ...
  • Gamma-ray detector based on high pressure xenon for radiation and environmental safety 
    Kutny, V.E.; Rybka, A.V.; Davydov, L.N.; Pudov, A.O.; Sokolov, S.A.; Kholomeyev, G.A.; Melnikov, S.I.; Turchin, A.A. (Вопросы атомной науки и техники, 2017)
    Gamma-spectrometers based on compressed xenon gas assigned for monitoring the reactors and the radiation background at nuclear power plants, non-proliferation of radioactive materials, supervision and control over the ...
  • Improvement of microstructure and mechanical properties of high dense SiC ceramics manufactured by high-speed hot pressing 
    Voyevodin, V.; Sayenko, S.; Lobach, K.; Tarasov, R.; Zykova, A.; Svitlychnyi, Ye.; Surkov, A.; Abelentsev, V.; Ghaemi, H.; Szkodo, M.; Gajowiec, G.; Kmiec, M.; Antoszkiewicz, M. (Вопросы атомной науки и техники, 2017)
    Non-oxide ceramics possess high physical-mechanical properties, corrosion and radiation resistance, which can be used as a protective materials for radioactive wastes disposal. The aim of the present study was the manufacturing ...
  • Nuclear reactor on cylindrical standing burning wave with an external negative reactivity feedback 
    Leleko, Yu.Y.; Gann, V.V.; Gann, A.V. (Вопросы атомной науки и техники, 2017)
    Neutron kinetics of nuclear burning wave in moving incompressible neutron-multiplying medium in the pres-ence of nuclear reactions is developed. A cylindrical reactor is considered, where the burning wave moves radially ...
  • Phase formation and characteristics of dysprosium titanate pellets prepared by solid state synthesis 
    Chernov, I.O.; Belash, M.M.; Kolodiy, I.V.; Valezhnyi, Ye.B.; Kalchenko, O.S.; Slabospitska, O.O. (Вопросы атомной науки и техники, 2017)
    Dysprosium titanate have been developed and used as absorbing material for control rods of thermal neutron nuclear reactors. The study results of phase formation kinetics in the pellets prepared from powder mixtures ...
  • Safety issues of the dry storage of the spent nuclear fuel 
    Alyokhina, S.; Kostikov, A.; Kruhlov, S. (Вопросы атомной науки и техники, 2017)
    Some issues of safety of the unique in Ukraine the Dry Spent Nuclear Fuel Storage Facility are highlighted. The analysis of temperature measurements of air, which cools storage containers of the spent nuclear fuel on the ...
  • The features of formation of the surface gradient layers in zirconium 
    Kirichenko, V.G.; Yampolskyi, O.O. (Вопросы атомной науки и техники, 2017)
    It was found that increasing the surface concentration of iron atoms in zirconium alloys in the surface layer thickness up to 0.3 μm results to the formation of gradient structures. This process can help to optimize the ...
  • The methods for the calculation of the elastic interaction of point defects with a dislocation loops in hexagonal crystals 
    Trotsenko, O.G.; Ostapchuk, P.N. (Вопросы атомной науки и техники, 2017)
    Green's function method is used for hexagonal crystals according to Lifshitz-Rosenzweig and Kröner. Analytical expressions have been derived for the energy of elastic interaction of radiation point defects with dislocation ...
  • Water-chemistry operating condition of the second circuit power units №1-4 Rivne NPP with ethanolamine`s corrective treatment 
    Kuznetsov, P.N.; Tichomirov, A.U. (Вопросы атомной науки и техники, 2017)
    The analysis of ethanolamine (ETA) operation results water-chemistry condition (WCC) of the second circuit power units No 1-4 Rivne NPP was provided. The control data in the experimental and industrial exploitation ETA WCC ...

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