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Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow

Atomic energy (New York, N.Y.), 2021-06, Vol.130 (2), p.76-81

2021

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Fabrication and study of the properties of PuO2−MgO fuel pellets

Atomic energy (New York, N.Y.), 1997-05, Vol.82 (5), p.347-350

1997

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Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor

Atomic energy (New York, N.Y.), 2017-10, Vol.122 (6), p.390-395

2017

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Distillation22Na separation from proton-irradiated aluminum targets

Atomic energy (New York, N.Y.), 2000-03, Vol.88 (3), p.233-235

2000

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Production of 10Be isotope from boron carbide irradiated with fast neutrons

Instruments and experimental techniques (New York), 2010-11, Vol.53 (6), p.777-782

2010

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Possibility of Obtaining 10Be from Spent Control Rods from Fast Reactors

Atomic energy (New York, N.Y.), 2000-08, Vol.89 (2), p.668-672

2000

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Release of fission products from the reactor fuel of the bilibinsk nuclear power plant under conditions which simulate a severe accident

Atomic energy (New York, N.Y.), 1993-05, Vol.74 (5), p.380-384

1993

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Fabrication and study of the properties of PuO2-MgO fuel pellets

Atomic energy (New York, N.Y.), 1997, Vol.82 (5), p.347-350

1997

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Distillation 22Na separation from proton-irradiated aluminum targets

Atomic energy (New York, N.Y.), 2000, Vol.88 (3), p.233-235

2000

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Separation of exp 22 Na from proton irradiated aluminum targets by the distillation method

Atomnaâ ėnergiâ, 2000-03, Vol.88 (3), p.226-228

2000

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Possibility of obtaining 10Be from spent control rods from fast reactors

Atomic energy (New York, N.Y.), 2000, Vol.89 (2), p.668-672

2000

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Fabrication and study of the properties of PuO sub(2)-MgO fuel pellets

Atomic energy (New York, N.Y.), 1997-05, Vol.82 (5), p.347-350

1997

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Investigation of uranium monocarbide fuel elements in the fuel bundles of the Br-5 reactor

Soviet Atomic Energy, 1971-01, Vol.30 (1), p.1-5

1971

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Distillation super(22)Na separation from proton-irradiated aluminum targets

Atomic energy (New York, N.Y.), 2000-03, Vol.88 (3), p.233-235

2000

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Gas-chromatographic examination of the accumulation of3H,85Kr, and133Xe in the protective gas, sodium coolant, and constructional materials of the BR-10

Soviet Atomic Energy, 1979-10, Vol.47 (4), p.847-849

1979

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Design and Antioxidant Properties of Bifunctional 2H-Imidazole-Derived Phenolic Compounds—A New Family of Effective Inhibitors for Oxidative Stress-Associated Destructive Processes

Molecules (Basel, Switzerland), 2021-10, Vol.26 (21), p.6534

2021

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On plutonium-241 and americium in the two-component nuclear energy system

Nuclear energy and technology, 2024-10, Vol.10 (4), p.235-240

2024

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Orbit tomography in constants-of-motion phase-space

Nuclear fusion, 2024-07, Vol.64 (7), p.76018

2024

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Diagnostic weight functions in constants-of-motion phase-space

Nuclear fusion, 2024-03, Vol.64 (3), p.36007

2024

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System features of fast sodium reactors in a two-component structure of nuclear power generating

Nuclear energy and technology, 2024-07, Vol.10 (2), p.105-110

2024

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Development of the 174 GHz collective Thomson scattering diagnostics at Wendelstein 7-X

Review of scientific instruments, 2024-01, Vol.95 (1)

2024

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4D and 5D phase-space tomography using slowing-down physics regularization

Nuclear fusion, 2023-07, Vol.63 (7), p.76016

2023

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Fast-ion velocity-space tomography using slowing-down regularization in EAST plasmas with co- and counter-current neutral beam injection

Plasma physics and controlled fusion, 2020-11, Vol.62 (11), p.115019

2020

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Some economic aspects of reducing americium production in a two-component system of thermal and fast reactors

Nuclear energy and technology, 2023-12, Vol.9 (4), p.253-258

2023

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The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System

Atomic energy (New York, N.Y.), 2022-12, Vol.133 (2), p.72-78

2022

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Investigation of Fission Product Release from Irradiated Oxide and Nitride Nuclear Fuel on High-Temperature Heating in Helium Flow

Fabrication and study of the properties of PuO2−MgO fuel pellets

Experimental and Computational Investigation of the Emission of Radioactive Products from Irradiated Fuel of Fast Sodium-Cooled Reactor

Distillation22Na separation from proton-irradiated aluminum targets

Production of 10Be isotope from boron carbide irradiated with fast neutrons

Possibility of Obtaining 10Be from Spent Control Rods from Fast Reactors

Release of fission products from the reactor fuel of the bilibinsk nuclear power plant under conditions which simulate a severe accident

Fabrication and study of the properties of PuO2-MgO fuel pellets

Distillation 22Na separation from proton-irradiated aluminum targets

Separation of exp 22 Na from proton irradiated aluminum targets by the distillation method

Possibility of obtaining 10Be from spent control rods from fast reactors

Fabrication and study of the properties of PuO sub(2)-MgO fuel pellets

Investigation of uranium monocarbide fuel elements in the fuel bundles of the Br-5 reactor

Distillation super(22)Na separation from proton-irradiated aluminum targets

Gas-chromatographic examination of the accumulation of3H,85Kr, and133Xe in the protective gas, sodium coolant, and constructional materials of the BR-10

Design and Antioxidant Properties of Bifunctional 2H-Imidazole-Derived Phenolic Compounds—A New Family of Effective Inhibitors for Oxidative Stress-Associated Destructive Processes

On plutonium-241 and americium in the two-component nuclear energy system

Orbit tomography in constants-of-motion phase-space

Diagnostic weight functions in constants-of-motion phase-space

System features of fast sodium reactors in a two-component structure of nuclear power generating

Development of the 174 GHz collective Thomson scattering diagnostics at Wendelstein 7-X

4D and 5D phase-space tomography using slowing-down physics regularization

Fast-ion velocity-space tomography using slowing-down regularization in EAST plasmas with co- and counter-current neutral beam injection

Some economic aspects of reducing americium production in a two-component system of thermal and fast reactors

The Initial Stage of Closing the NFC of the Russian Two-Component Nuclear Power Engineering System

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