Resultats de la cerca - 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

    Publicat 2019
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  2. 2
    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Publicat 2019
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2020
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2019
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2019
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2020
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2020
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2022
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2021
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre
  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

    Publicat 2023
    Altres autors: Obtenir text complet
    Electrònic Capítol de llibre

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