Перегляд за автором "Svichkar, A.S."

Сортувати за: Порядок: Результатів:

  • Yuferov, V.B.; Katrechko, V.V.; Mufel, E.V.; Svichkar, A.S.; Ilichova, V.O.; Khizhnyak, S.N.; Shariy, S.V. (Вопросы атомной науки и техники, 2014)
    The analysis of the multicomponent composition of spent nuclear fuel (SNF) is presented. The possibility of SNF separation from the fission products (FP) upon heating, evaporation and ionization (at difference of the ...
  • Katrechko, V.V.; Yuferov, V.B.; Svichkar, A.S.; Tkachova, T.I.; Shariy, S.V.; Ilichova, V.O. (Вопросы атомной науки и техники, 2016)
    Stage ionization is an intermediate stage separation of spent nuclear fuel (SNF) between heating stage and magnetoplasma separation of fission products (FP) and nuclear fuel (NF) in rotating plasma. The process of plasma ...
  • Yuferov, V.B.; Katrechko, V.V.; Svichkar, A.S.; Shariy, S.V.; Tkachova, T.I.; Mufel, E.V.; Ilichova, V.О.; Pakhomov, А.Yu. (Вопросы атомной науки и техники, 2016)
    The possibility of multicomponent mixtures separation at thermal heating, ionization and plasma rotation in relation to the spent nuclear fuel (SNF) is shown. At thermal heating it is possible to allocate up to 75% of ...
  • Yuferov, V.B.; Katrechko, V.V.; Tkachova, T.I.; Shariy, S.V.; Svichkar, A.S.; Mufel, E.V.; Ilichova, V.О.; Shvets, M.O. (Вопросы атомной науки и техники, 2015)
    Possible composition of spent nuclear fuel (SNF) before and after the thermal separation stage is shown. The possibility of SNF purification from fission products (FP) at the ionization stage is analyzed. Trajectories of ...
  • Yuferov, V.B.; Tkachova, T.I.; Katrechko, V.V.; Svichkar, A.S.; Ilichova, V.O.; Shariy, S.V. (Вопросы атомной науки и техники, 2017)
    Trajectories of charged particles (UO₂ and La₂O₃) at magnetoplasma separation stage – in system of crossed electric and magnetic fields – are calculated. The possibilities of UO₂ separation from La₂O₃ by changes in magnetic ...
  • Yuferov, V.B.; Ilichova, V.O.; Katrechko, V.V.; Shariy, S.V.; Svichkar, A.S.; Shvets, M.O.; Tkachov, V.I.; Vinnikov, D.V.; Ozerov, A.N. (Вопросы атомной науки и техники, 2018)
    The design of a demo-imitation separator is presented which is the model of a plasma filter for the masses of irradiated oxide uranium fuel. Expected setup productivity is ~15…20 tons/year of the material – imitator, that ...
  • Yuferov, V.B.; Katrechko, V.V.; Ilichova, V.O.; Shariy, S.V.; Svichkar, A.S.; Shvets, M.O.; Buravilov, I.V.; Khizhnyak, S.N. (Вопросы атомной науки и техники, 2017)
    Some problems on formation of the complex chemical compounds (uranate, zirconate, etc.) in the fuel rods during irradiation and in oxidative reactions are considered. Complex compounds in uence the separation processes at ...
  • Shariy, S.V.; Yuferov, V.B.; Tkachova, T.I.; Svichkar, A.S.; Shvets, M.O.; Tkachov, V.I. (Вопросы атомной науки и техники, 2015)
    An experimental study of the influence of HF power and configuration of the magnetic field on the plasma parameters of the gas source with incandescent cathode was carried out. It is shown that the application HF power ...
  • Yuferov, V.B.; Shariy, S.V.; Tkachova, T.I.; Katrechko, V.V.; Svichkar, A.S.; Ilichova, V.O.; Shvets, M.O.; Mufel, E.V. (Вопросы атомной науки и техники, 2017)
    At present the recycling of nuclear fuel (NF), i.e. its reuse, is implemented by using PUREX-process. However, it leads to increase of liquid radioactive waste (RW) volume, while the alternative methods of physical ...