Resultados da busca - Lutsik I. O. Igor Olegovich

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  1. 1
    A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics

    A fuel for generation IV nuclear energy system: Isotopic composition and radiation characteristics

    Publicado em 2019
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  2. 2
    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Publicado em 2019
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  3. 3
    Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap

    Power density dynamics in a nuclear reactor with an extended in-core pulse-periodic neutron source based on a magnetic trap

    Publicado em 2020
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  4. 4
    Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation

    Neutron-physical studies of ceramic fuel of a hightemperature reactor in the regime of long-term operation

    Publicado em 2019
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  5. 5
    Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons

    Gas-cooled thorium reactor at various fuel loadings and its modification by a plasma source of extra neutrons

    Publicado em 2019
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  6. 6
    Nedis-Serpent simulation of a neutron source assembly with complex internal heterogeneous structure

    Nedis-Serpent simulation of a neutron source assembly with complex internal heterogeneous structure

    Publicado em 2020
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  7. 7
    Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap

    Facility to study neutronic properties of a hybrid thorium reactor with a source of thermonuclear neutrons based on a magnetic trap

    Publicado em 2020
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  8. 8
    Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration

    Fusion-fission hybrid reactor with a plasma source of deuterium-tritium neutrons in a linear configuration

    Publicado em 2022
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  9. 9
    Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

    Maintaining the close-to-critical state of thorium fuel core of hybrid reactor operated under control by D-T fusion neutron flux

    Publicado em 2021
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro
  10. 10
    Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation

    Neutronic and thermohydraulic blanket analysis for hybrid fusion–fission reactor during operation

    Publicado em 2023
    Outros Autores: Obter o texto integral
    Recurso Eletrônico Capítulo de Livro

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