Search Results - 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

    Published 2019
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    Electronic Book Chapter
  2. 2
    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Peculiarities of the radiation formation in dispersed microencapsulated nuclear fuel

    Published 2019
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    Electronic Book Chapter
  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

    Published 2020
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    Electronic Book Chapter
  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

    Published 2019
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    Electronic Book Chapter
  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

    Published 2019
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    Electronic Book Chapter
  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

    Published 2020
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    Electronic Book Chapter
  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

    Published 2020
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    Electronic Book Chapter
  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

    Published 2022
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    Electronic Book Chapter
  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

    Published 2021
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    Electronic Book Chapter
  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

    Published 2023
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    Electronic Book Chapter

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