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Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation

Fusion engineering and design, 2021-11, Vol.172, p.112783, Article 112783

2021

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Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method

Fusion engineering and design, 2021-09, Vol.170, p.112705, Article 112705

2021

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Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor

IEEE transactions on nuclear science, 2020-10, Vol.67 (10), p.2162-2171

2020

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Radiation resistance of single-mode optical fibres with view to in-reactor applications

Nuclear materials and energy, 2021-06, Vol.27, p.100981, Article 100981

2021

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Effect of low-temperature neutron irradiation on the properties of titanium beryllide

Nuclear materials and energy, 2024-03, Vol.38, p.101582, Article 101582

2024

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Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation

Bulletin of the Lebedev Physics Institute, 2023-09, Vol.50 (Suppl 3), p.S322-S328

2023

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Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium

Journal of nuclear materials, 2013-11, Vol.442 (1-3), p.S740-S745

2013

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Reactor studies of tritium release from lead-lithium eutectic Li15.7Pb with deuterium over the sample

Nuclear materials and energy, 2020-12, Vol.25, p.100868, Article 100868

2020

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Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

Fusion engineering and design, 2017-11, Vol.124, p.324-327

2017

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Experimental facility for reactor experiments on study of spectral-luminescent characteristics of nuclear-excited plasma

Journal of physics. Conference series, 2016-09, Vol.747 (1), p.12012

2016

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Development of the reactor lithium ampoule device for research of spectral-luminescent characteristics of nuclear-excited plasma

Fusion engineering and design, 2017-04, Vol.117, p.204-207

2017

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Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests)

Fusion engineering and design, 2006-02, Vol.81 (1-7), p.701-705

2006

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Study of Li2TiO3 + 5 mol% TiO2 lithium ceramics after long-term neutron irradiation

Journal of nuclear materials, 2009-04, Vol.386-88, p.286-289

2009

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Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.748-752

2011

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Studies of reactor irradiation effect on hydrogen isotope release from vanadium alloy V4Cr4Ti

Journal of nuclear materials, 2007-08, Vol.367, p.844-847

2007

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Material science activities for fusion reactors in Kazakhstan

Journal of nuclear materials, 2009-04, Vol.386, p.15-18

2009

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Experiments on tritium generation and yield from lithium ceramics during neutron irradiation

International journal of hydrogen energy, 2021-02, Vol.46 (13), p.9186-9192

2021

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Reactor experiments on irradiation of two-phase lithium ceramics Li2TiO3/Li4SiO4 of various ratios

Fusion engineering and design, 2023-12, Vol.197, p.114035, Article 114035

2023

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Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor

Journal of nuclear materials, 2007-08, Vol.367-370, p.1028-1032

2007

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In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4

Fusion engineering and design, 2007-10, Vol.82 (15-24), p.2246-2251

2007

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Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)

International journal of hydrogen energy, 2022-02, Vol.47 (11), p.7368-7378

2022

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The temperature-time dependence of the amount and type of niobium beryllides formed during the synthesis of the binary intermetallic compound NbBe3

Intermetallics, 2023-12, Vol.163, p.108065, Article 108065

2023

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Study of interaction of hydrogen isotopes with titanium beryllide (Be12Ti)

Fusion engineering and design, 2023-06, Vol.191, p.113738, Article 113738

2023

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Irradiation experiments of titanium beryllide samples in the WWR-K reactor

Annals of nuclear energy, 2023-12, Vol.194, p.110120, Article 110120

2023

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Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation

Optical fiber technology, 2023-10, Vol.80, p.103441, Article 103441

2023

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Determination of the activation energy of tritium diffusion in ceramic breeders by reactor power variation

Modeling of hydrogen isotopes release from lithium ceramics Li2TiO3 during in-situ experiments using vacuum extraction method

Radiation Resistance of Single-Mode Optical Fibers at λ = 1.55 μm Under Irradiation at IVG.1M Nuclear Reactor

Radiation resistance of single-mode optical fibres with view to in-reactor applications

Effect of low-temperature neutron irradiation on the properties of titanium beryllide

Radiation Resistance of Fiber Bragg Gratings under Intense Reactor Irradiation

Tritium migration in the materials proposed for fusion reactors: Li2TiO3 and beryllium

Reactor studies of tritium release from lead-lithium eutectic Li15.7Pb with deuterium over the sample

Investigation of hydrogen isotopes interaction with lithium CPS under reactor irradiation

Experimental facility for reactor experiments on study of spectral-luminescent characteristics of nuclear-excited plasma

Development of the reactor lithium ampoule device for research of spectral-luminescent characteristics of nuclear-excited plasma

Investigation of hydrogen isotope permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4 (out-of-pile tests)

Study of Li2TiO3 + 5 mol% TiO2 lithium ceramics after long-term neutron irradiation

Tritium accumulation and release from Li2TiО3 during long-term irradiation in the WWR-K reactor

Studies of reactor irradiation effect on hydrogen isotope release from vanadium alloy V4Cr4Ti

Material science activities for fusion reactors in Kazakhstan

Experiments on tritium generation and yield from lithium ceramics during neutron irradiation

Reactor experiments on irradiation of two-phase lithium ceramics Li2TiO3/Li4SiO4 of various ratios

Measurement system for in-pile tritium monitoring from Li2TiO3 ceramics at WWRK reactor

In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr2O3-SiO2 including CrPO4

Analysis of reactor experiments to study the transfer processes of generated tritium in lithium cps (capillary-porous system)

The temperature-time dependence of the amount and type of niobium beryllides formed during the synthesis of the binary intermetallic compound NbBe3

Study of interaction of hydrogen isotopes with titanium beryllide (Be12Ti)

Irradiation experiments of titanium beryllide samples in the WWR-K reactor

Radiation-induced attenuation in single-mode pure-silica-core optical fibers two years after high-fluence reactor irradiation

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