Перегляд за автором "Chernitskiy, S.V."

Сортувати за: Порядок: Результатів:

  • A fuel cycle for minor actinides burning in a stellarator-mirror fusion-fission hybrid 
    Chernitskiy, S.V.; Moiseenko, V.E.; Ågren, O.; Noack, K. (Вопросы атомной науки и техники, 2017)
    The MCNPX Monte-Carlo code has been used to model a concept of a fusion-fission stellarator-mirror hybrid aimed for transmutation transuranic content from the spent nuclear fuel. A fuel cycle for the subcritical fusion-fission ...
  • 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 ...
  • Minor actinides burning in a stellarator-mirror fusion-fission hybrid 
    Chernitskiy, S.V.; Moiseenko, V.E.; Ågren, O.; Noack, K. (Вопросы атомной науки и техники, 2015)
    The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation ...
  • Multiple recycle fuel cycle for spent nuclear fuel components incineration in fusion-fission hybrid 
    Moiseenko, V.Е.; Chernitskiy, S.V.; Ågren, O. (Problems of Atomic Science and Technology, 2022)
    A multiple recycle fuel cycle (MRFC) is analyzed using a simple numerical model. A straightforward approach to MRFC has some unfavorable features like strong variation of the neutron multiplication factor and accumulation ...
  • Neutronic model of a fusion neutron source 
    Chernitskiy, S.V.; Moiseenko, V.E.; Ågren, O.; Noack, K.; Abdullayev, A. (Вопросы атомной науки и техники, 2013)
    The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellaratormirror trap. Calculation results for the neutron spectrum near the inner wall and radial leakage of neutrons through ...
  • Neutronic model of a stellarator-mirror fusion-fission hybrid 
    Chernitskiy, S.V.; Moiseenko, V.E.; Noack, K.; Ågren, O.; Abdullayev, A. (Вопросы атомной науки и техники, 2012)
    The MCNPX numerical code has been used to model a compact concept for a fusion-fission reactor based on a combined stellarator-mirror trap. Calculation results for the radial leakage of neutrons through the mantle surface ...
  • Static neutronic calculation of a fusion neutron source 
    Chernitskiy, S.V.; Gann, V.V.; Ågren, O. (Вопросы атомной науки и техники, 2014)
    The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and ...
  • Steady-state fusion fission reactor concepts based on stellarator-mirror and mirror machines 
    Ågren, O.; Moiseenko, V.E.; Noack, K.; Chernitskiy, S.V. (Вопросы атомной науки и техники, 2015)
    Neutron sources and hybrid reactors offer a possibility for application of fusion in a not too distant future. Steady-state operation on a time scale of a year without interruption is essential for such applications. In ...
  • Tritium breeding calculation in a stellarator blanket 
    Chernitskiy, S.V.; Moiseenko, V.E. (Вопросы атомной науки и техники, 2019)
    In current blanket projects, tritium breeding ratio (TBR), the ratio of tritium production rate to the neutron production rate, is low (1.1…1.2). The MCNPX Monte-Carlo code has been used to model the neutron kinetics and ...