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Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP

Physics of atomic nuclei, 2022-12, Vol.85 (Suppl 2), p.S90-S102

2022

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Comparing Metrological Characteristics of Methodologies for Determining Uranium Enrichment Using NaI and LEGe Detectors

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12067

2020

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Investigation of radioactive reactor graphite by gamma-spectrometric method

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12073

2020

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Experience of long-term U-Al fuel performance in research reactors with low energy generation

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12024

2020

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Analysis of Methods and Technologies for Composition Assessing of Corium Formed as a Result of the Fukushima Daiichi NPP Accident

Глобальная ядерная безопасность, 2022-09 (3), p.5-21

2022

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A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors

Physics of atomic nuclei, 2016-12, Vol.79 (8), p.1362-1366

2016

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Mathematical Modeling of the γ-Ray Spectra of Fuel Pins with Uranium-Plutonium Fuel for Development of Fissile-Materials Monitoring Procedures

Atomic energy (New York, N.Y.), 2018-12, Vol.125 (2), p.108-111

2018

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Gamma-Spectrometric Control of Fissile Mass and Distribution Uniformity in Fuel Pins with Uranium-Plutonium Nitride Fuel

Atomic energy (New York, N.Y.), 2018-12, Vol.125 (2), p.103-107

2018

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Radioactive Contamination of Spent Reactor Graphite

Atomic energy (New York, N.Y.), 2015-01, Vol.117 (3), p.196-200

2015

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Gamma-Spectrometric Determination of the Plutonium Mass in Containers

Atomic energy (New York, N.Y.), 2016-02, Vol.119 (4), p.253-257

2016

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Methods of Inspecting the Radioactive Contamination of Uranium-Graphite Reactor Masonry

Atomic energy (New York, N.Y.), 2016-05, Vol.120 (1), p.44-47

2016

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Determination of the residual content of fissile materials in fuel from spent fuel assemblies with high initial enrichment by the active neutron method

Atomic energy (New York, N.Y.), 2013-10, Vol.114 (6), p.428-432

2013

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Numerical simulation of plutonium measurements using an active well coincidence counter (AWCC)

Atomic energy (New York, N.Y.), 2024-11

2024

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Gamma spectrometric determination of the isotopic decomposition of plutonium in containers using MGA and FRAM software

Atomic energy (New York, N.Y.), 2012-12, Vol.113 (2), p.117-124

2012

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Determination of the plutonium mass in containers with plutonium dioxide according to the γ radiation from spontaneous-fission products

Atomic energy (New York, N.Y.), 2010-05, Vol.108 (1), p.46-52

2010

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Experimental study of the radioactive contamination of graphite masonry in the commercial reactors at the siberian chemical combine

Atomic energy (New York, N.Y.), 2002-06, Vol.92 (6), p.514-522

2002

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Development of the method of isotopic correlations for determining the relative (242)Pu content in plutonium samples

Atomic energy (New York, N.Y.), 2009-06, Vol.106 (6), p.423-426

2009

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Development of the method of isotopic correlations for determining the relative 242Pu content in plutonium samples

Atomic energy (New York, N.Y.), 2009-06, Vol.106 (6), p.423-426

2009

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Possibility of Salvaging Spent Graphite Sleeves from the Reactors of the Siberian Chemical Combine by Incineration

Atomic energy (New York, N.Y.), 2003-02, Vol.94 (2), p.91-98

2003

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DETERMINATION OF IRT FA BURNUP AT MEPHI FROM TOTAL [sup.137]Cs ACTIVITY

Atomic energy (New York, N.Y.), 2017-07, Vol.122 (3), p.213

2017

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Determination of IRT FA Burnup at Mephi from Total 137Cs Activity

Atomic energy (New York, N.Y.), 2017-07, Vol.122 (3), p.213-215

2017

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Fission Products and Actinides in Spent Graphite Masonry of the Reactors at the Siberian Chemical Combine

Atomic energy (New York, N.Y.), 2000-08, Vol.89 (2), p.650-657

2000

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C in spent graphite from uranium-graphite reactors at the Siberian chemical combine

Atomic energy (New York, N.Y.), 2012-05, Vol.112 (1), p.63

2012

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Comparison of correlation relations for determining the relative [sup.242]Pu content in plutonium produced in the RT-1 plant at the Industrial Association Mayak

Atomic energy (New York, N.Y.), 2013-08, Vol.114 (4), p.249

2013

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Comparison of correlation relations for determining the relative 242Pu content in plutonium produced in the RT-1 plant at the Industrial Association Mayak

Atomic energy (New York, N.Y.), 2013-08, Vol.114 (4), p.249-253

2013

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Analysis of Methods and Technologies for Assessing the Composition of the Corium Formed as a Result of the Accident at the Fukushima Daiichi NPP

Comparing Metrological Characteristics of Methodologies for Determining Uranium Enrichment Using NaI and LEGe Detectors

Investigation of radioactive reactor graphite by gamma-spectrometric method

Experience of long-term U-Al fuel performance in research reactors with low energy generation

Analysis of Methods and Technologies for Composition Assessing of Corium Formed as a Result of the Fukushima Daiichi NPP Accident

A setup for active neutron analysis of the fissile material content in fuel assemblies of nuclear reactors

Mathematical Modeling of the γ-Ray Spectra of Fuel Pins with Uranium-Plutonium Fuel for Development of Fissile-Materials Monitoring Procedures

Gamma-Spectrometric Control of Fissile Mass and Distribution Uniformity in Fuel Pins with Uranium-Plutonium Nitride Fuel

Radioactive Contamination of Spent Reactor Graphite

Gamma-Spectrometric Determination of the Plutonium Mass in Containers

Methods of Inspecting the Radioactive Contamination of Uranium-Graphite Reactor Masonry

Determination of the residual content of fissile materials in fuel from spent fuel assemblies with high initial enrichment by the active neutron method

Numerical simulation of plutonium measurements using an active well coincidence counter (AWCC)

Gamma spectrometric determination of the isotopic decomposition of plutonium in containers using MGA and FRAM software

Determination of the plutonium mass in containers with plutonium dioxide according to the γ radiation from spontaneous-fission products

Experimental study of the radioactive contamination of graphite masonry in the commercial reactors at the siberian chemical combine

Development of the method of isotopic correlations for determining the relative (242)Pu content in plutonium samples

Development of the method of isotopic correlations for determining the relative 242Pu content in plutonium samples

Possibility of Salvaging Spent Graphite Sleeves from the Reactors of the Siberian Chemical Combine by Incineration

DETERMINATION OF IRT FA BURNUP AT MEPHI FROM TOTAL [sup.137]Cs ACTIVITY

Determination of IRT FA Burnup at Mephi from Total 137Cs Activity

Fission Products and Actinides in Spent Graphite Masonry of the Reactors at the Siberian Chemical Combine

C in spent graphite from uranium-graphite reactors at the Siberian chemical combine

Comparison of correlation relations for determining the relative [sup.242]Pu content in plutonium produced in the RT-1 plant at the Industrial Association Mayak

Comparison of correlation relations for determining the relative 242Pu content in plutonium produced in the RT-1 plant at the Industrial Association Mayak

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