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Перегляд Вопросы атомной науки и техники, 2017, № 2 за назвою

Репозиторій DSpace/Manakin

Перегляд Вопросы атомной науки и техники, 2017, № 2 за назвою

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. ...
  • Application of hydrogen embritlement models to the blister growth behavior in 12Cr2MoNbVB steel and α -Fe exposed to low-energy D plasma 
    Nikitin, A.V.; Tolstolutskaya, G.D.; Ruzhytskiy, V.V.; Kopanets, I.E.; Karpov, S.A.; Vasilenko, R.L.; Rostova, G.Y.; Rybalchenko, N.D.; Sungurov, B.S. (Вопросы атомной науки и техники, 2017)
    Processes of blisters and associated subsurface cracks nucleation during exposure of 12Cr2MoNbVB ferritic-martensitic steel and α-Fe under glow discharge hydrogen (deuterium) plasma with ion energies of ~ 1 keV and ion ...
  • 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 ...
  • Effect of deuterium implantation dose on properties of CrN coatings 
    Kuprin, A.S.; Belous, V.A.; Morozov, O.M.; Ovcharenko, V.D.; Dub, S.N.; Tolmachova, G.N.; Reshetnyak, E.N.; Zhurba, V.I.; Progolaieva, V.O. (Вопросы атомной науки и техники, 2017)
    The methods of X-ray diffraction analysis, atomic-force microscopy, nanoindentation and thermodesorption spectroscopy have been applied to investigate the effect of a dose (from 5∙10¹⁶ to 1.5∙10¹⁸ D/сm²) of implanted ...
  • 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 ...
  • Microstructure evolution and deuterium trapping in low-energy cascades after irradiation of SS316 stainless steel 
    Karpov, S.A.; Tolstolutskaya, G.D.; Sungurov, B.S.; Ruzhytskiy, V.V. (Вопросы атомной науки и техники, 2017)
    The release profile of deuterium from SS316 austenitic steel irradiated with low-energy deuterium ions was studied using thermal desorption spectroscopy as well as steel microstructure evolution after deuterium implantation ...
  • 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 ...
  • Optimization of technology for fabrication of sectional nuclear radiation detectors based on high-resistance silicon 
    Gaidar, G.P.; Berdnichenko, S.V.; Vorobyov, V.G.; Kochkin, V.I.; Lastovetskiy, V.F.; Litovchenko, P.G. (Вопросы атомной науки и техники, 2017)
    On the basis of experimental studies the surface-barrier technology for fabrication of sectional nuclear radiation detectors with using of the high-resistance n-Si plates of large diameter (~ 100 mm) was optimized. The ...
  • 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 ...
  • Problem of evaluation for structural materials operability in elements of nuclear power plants equipments 
    Yefimov, A.V.; Romashov, Yu.V. (Вопросы атомной науки и техники, 2017)
    It is presented the review of published data about different dangerous damaging of critical equipment at a nuclear power unit during industrial operation, which indicate the urgency of the problem of evaluation of structural ...
  • Regularities of radiation and heterogeneous processes in contact of Zr and Zr1%Nb alloy with water 
    Agayev, T.N.; Faradj-zadeh, I.A.; Aliyev, A.G.; Eyubov, K.T.; Aliyev, S.M. (Вопросы атомной науки и техники, 2017)
    Influence of radiation in the processes of hydrogen accumulation and zirconium oxidation as a result of heterogeneous processes in contact of zirconium and a Zr1%Nb alloy with water vapors is investigated. The contribution ...
  • Role of surface layer nanosrtucturing in improving mechanical and corrosion properties of reactor materials 
    Ozhigov, L.S.; Belous, V.A.; Savchenko, V.I.; Nosov, G.I.; Ovcharenko, V.D.; Tolmachova, G.N.; Kuprin, A.S.; Goltvyanitsa, V.S. (Вопросы атомной науки и техники, 2017)
    The results of investigations into the influence of the ion-plasma treatment (IPT), including the ion implantation and ion-plasma coating deposition, on the mechanical properties and corrosion resistance of nuclear fuel ...
  • 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 ...
  • Study of desorption process from the Zr (62) – Ni (38 wt.%) non-evaporable getter 
    Aksyonova, G.N.; Bobrov, Yu.P.; Pylypenko, M.M.; Svynarenko, A.P. (Вопросы атомной науки и техники, 2017)
    The gas desorption process from the Zr (62) – Ni (38 wt.%) non-evaporable getter produced by the calciothermal technology have been studied. The comparison between the thermostimulated desorption spectra of the samples, ...
  • 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 ...

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