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Analysis of lutetium-177 production at the WWR-K research reactor

Applied radiation and isotopes, 2021-03, Vol.169, p.109561-109561, Article 109561

2021

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Time History of Performance Parameters of WWR-K Reactor during Gradual Replacement of the Water Reflector by a Beryllium One

Russian physics journal, 2021-04, Vol.63 (12), p.2165-2177

2021

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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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Modeling the Processes of Hydrogen Isotopes Interactions with Solid Surfaces

Fusion science and technology, 2020-05, Vol.76 (4), p.494-502

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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Analysis of the Reactor Experiment Results on Irradiation of Lead-Lithium Eutectic

Fusion science and technology, 2020-07, Vol.76 (5), p.632-641

2020

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In-Pile Assemblies for Investigation of Tritium Release from Li2TiO3 Lithium Ceramic

Fusion science and technology, 2005-05, Vol.47 (4), p.1084-1088

2005

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In-Pile Assemblies for Investigation of Tritium Release from Li{sub 2}TiO{sub 3} Lithium Ceramic

Fusion science and technology, 2005-05, Vol.47 (4)

2005

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In-Pile Assemblies for Investigation of Tritium Release from Li 2 TiO 3 Lithium Ceramic

Fusion science and technology, 2005-05, Vol.47 (4), p.1084-1088

2005

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Aluminothermic Synthesis of Dispersed Electrides Based on Mayenite: XRD and EPR Study

Materials, 2022-12, Vol.15 (24), p.8988

2022

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Effect of La Addition on the Performance of Three-Way Catalysts Containing Palladium and Rhodium

Topics in catalysis, 2020-03, Vol.63 (1-2), p.152-165

2020

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Synthesis and Investigation of Finely Dispersed Calcium Aluminates and Catalysts Based on Them

Russian journal of physical chemistry. B, 2022-06, Vol.16 (3), p.411-420

2022

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Interaction of Pd and Rh with ZrCeYLaO2 support during thermal aging and its effect on the CO oxidation activity

Reaction kinetics, mechanisms and catalysis, 2020-02, Vol.129 (1), p.117-133

2020

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Prospects of Using Ruthenium within the Composition of Three-Way Palladium–Rhodium Catalysts

Kinetika i kataliz, 2023-11, Vol.64 (6), p.853-856

2023

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Identification of the state of the soil-plant systems on the RUDN-University campus (based on PAH concentrations)

E3S web of conferences, 2020, Vol.169, p.1015

2020

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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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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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Temperature dependence of the rate constant of hydrogen isotope interactions with a lithium capillary-porous system under reactor irradiation

Fusion engineering and design, 2013-10, Vol.88 (9-10), p.1731-1734

2013

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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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ECONOMIC DEVELOPMENT OF AGRICULTURE IN THE REGION (BY THE EXAMPLE OF PAVLODAR REGION): CHALLENGES, STRATEGIES AND PROSPECTS

THE BULLETIN, 2023-08, Vol.4 (404), p.463-480

2023

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Material science activities for fusion reactors in Kazakhstan

Journal of nuclear materials, 2009, Vol.386-88, p.15-18

2009

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Hydrogen release from reactor-irradiated beryllium

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.837-840

1996

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Influence of loading method on hydrogen retention and release from beryllium

Journal of nuclear materials, 1998-10, Vol.258, p.798-802

1998

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Hydrogen release of reactor irradiated RGT-graphite

Journal of nuclear materials, 1996-10, Vol.233, p.1198-1201

1996

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Influence of loading method on hydrogen retention and release from beryllium

Journal of nuclear materials, 1997-10, Vol.258-263, p.798-802

1997

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Analysis of lutetium-177 production at the WWR-K research reactor

Time History of Performance Parameters of WWR-K Reactor during Gradual Replacement of the Water Reflector by a Beryllium One

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

Modeling the Processes of Hydrogen Isotopes Interactions with Solid Surfaces

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

Analysis of the Reactor Experiment Results on Irradiation of Lead-Lithium Eutectic

In-Pile Assemblies for Investigation of Tritium Release from Li2TiO3 Lithium Ceramic

In-Pile Assemblies for Investigation of Tritium Release from Li{sub 2}TiO{sub 3} Lithium Ceramic

In-Pile Assemblies for Investigation of Tritium Release from Li 2 TiO 3 Lithium Ceramic

Aluminothermic Synthesis of Dispersed Electrides Based on Mayenite: XRD and EPR Study

Effect of La Addition on the Performance of Three-Way Catalysts Containing Palladium and Rhodium

Synthesis and Investigation of Finely Dispersed Calcium Aluminates and Catalysts Based on Them

Interaction of Pd and Rh with ZrCeYLaO2 support during thermal aging and its effect on the CO oxidation activity

Prospects of Using Ruthenium within the Composition of Three-Way Palladium–Rhodium Catalysts

Identification of the state of the soil-plant systems on the RUDN-University campus (based on PAH concentrations)

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

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

Temperature dependence of the rate constant of hydrogen isotope interactions with a lithium capillary-porous system under reactor irradiation

Material science activities for fusion reactors in Kazakhstan

ECONOMIC DEVELOPMENT OF AGRICULTURE IN THE REGION (BY THE EXAMPLE OF PAVLODAR REGION): CHALLENGES, STRATEGIES AND PROSPECTS

Material science activities for fusion reactors in Kazakhstan

Hydrogen release from reactor-irradiated beryllium

Influence of loading method on hydrogen retention and release from beryllium

Hydrogen release of reactor irradiated RGT-graphite

Influence of loading method on hydrogen retention and release from beryllium

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