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Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations

Atomic energy (New York, N.Y.), 2022-02, Vol.131 (4), p.229-233

2022

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Computer Identification of Nuclear-Material Fragments: A Tool for Countering Illicit Trafficking

Atomic energy (New York, N.Y.), 2021-12, Vol.131 (2), p.114-119

2021

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Technologies for Safing the Semipalatinsk Test Site

Atomic energy (New York, N.Y.), 2020-12, Vol.129 (2), p.108-111

2020

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Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle

Atomic energy (New York, N.Y.), 2021-05, Vol.130 (1), p.53-56

2021

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Computer Trainer for Teaching International Inspectors to Search for the Footprints of Secret Nuclear Tests

Atomic energy (New York, N.Y.), 2016-08, Vol.120 (4), p.294-298

2016

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Validation of nuclear and radiation safety of a container for spent AMB reactor fuel assemblies at the beloyarskaya nuclear power plant

Atomic energy (New York, N.Y.), 2006-06, Vol.100 (6), p.394-399

2006

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Possibility of identifying the fuel elements and fuel assemblies of first-generation USA and USSR research reactors

Atomic energy (New York, N.Y.), 2013-02, Vol.113 (4), p.271-275

2013

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Current environmental challenges and nuclear power production with fast neutron reactors and closed fuel cycle

Iindustrial Ecology, 2022 (4), p.48-53

2022

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Calibration Experiment on the Detection of Fissioning Material in Soil by Means of Neutron Detection

Atomic energy (New York, N.Y.), 2005-09, Vol.99 (3), p.670-675

2005

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Computational-Experimental Study of the Heating of Structural Materials by IGRIK Radiation

Atomic energy (New York, N.Y.), 2005-03, Vol.98 (3), p.181-186

2005

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Measurement of the temperature of structural materials heated by radiation from a pulsed uranium-graphite reactor

Atomic energy (New York, N.Y.), 2001, Vol.90 (1), p.17-21

2001

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Monitoring of the movement of a melt of fissioning material in the experimental channel of a pulsed graphite reactor igr using small neutron detectors

Atomic energy (New York, N.Y.), 2002-03, Vol.92 (3), p.239-245

2002

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Increasing the Internal Protection of a Pulsed Reactor Against Wrong or Illegal Actions

Atomic energy (New York, N.Y.), 2003-05, Vol.94 (5), p.350-354

2003

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Computational Investigation of the Lifetime Characteristics of IGR Neutrons

Atomic energy (New York, N.Y.), 2004-01, Vol.96 (1), p.17-21

2004

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Expected Characteristics of the Multipurpose Pulsed Uranium-Graphite Reactor Complex

Atomic energy (New York, N.Y.), 2002-11, Vol.93 (5), p.866-871

2002

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PRIZMA.D computational investigation of physical processes in the IGR reactor

Atomic energy (New York, N.Y.), 2000-02, Vol.88 (2), p.81-87

2000

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Characteristics of the Thermal-Neutron Field in the Experimental Channel of a Pulsed Graphite Reactor

Atomic energy (New York, N.Y.), 2001-04, Vol.90 (4), p.261-266

2001

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Investigation of the neutron field in the central channel of a pulse graphite reactor when the neutron absorber moves

Atomic energy (New York, N.Y.), 1998-12, Vol.85 (6), p.907-910

1998

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Method for identifying 17-place casings with spent fuel assemblies of AMB reactors at the Beloyarskaya nuclear power plant

Atomic energy (New York, N.Y.), 2007-06, Vol.102 (6), p.452-457

2007

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Study of the three-dimensional neutron field in the core of the IGR (pulsed graphite reactor)

Atomic energy (New York, N.Y.), 1997-06, Vol.82 (6), p.403-408

1997

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Identification of the fuel parts of research reactors

Atomic energy (New York, N.Y.), 2007-04, Vol.102 (4), p.287-292

2007

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A computational-experimental investigation of the temperature field of IGR masonry

Atomic energy (New York, N.Y.), 2000-04, Vol.88 (4), p.251-256

2000

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Computational-Experimental Investigation of the Special Features of the Neutron Spectrum of an IGR Reactor

Atomic energy (New York, N.Y.), 2000-09, Vol.89 (3), p.750-754

2000

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Dual purpose transport packaging using 'coiled' technology for treatment of spent fuel from first and second units of Beloyarskaya nuclear power plant

Packaging, transport, storage & security of radioactive material, 2006-12, Vol.17 (4), p.203-207

2006

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“Bleaching” of uranium-graphite fuel for pulse graphite reactors

Atomic energy (New York, N.Y.), 1998-11, Vol.85 (5), p.845-848

1998

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Detection of Indications of Nuclear Non-Proliferation Breaches By States Importing Fast Reactors with Closed NFC Installations

Computer Identification of Nuclear-Material Fragments: A Tool for Countering Illicit Trafficking

Technologies for Safing the Semipalatinsk Test Site

Nuclear Non-Proliferation Security on Exportation of Fast Reactors with a Closed Fuel Cycle

Computer Trainer for Teaching International Inspectors to Search for the Footprints of Secret Nuclear Tests

Validation of nuclear and radiation safety of a container for spent AMB reactor fuel assemblies at the beloyarskaya nuclear power plant

Possibility of identifying the fuel elements and fuel assemblies of first-generation USA and USSR research reactors

Current environmental challenges and nuclear power production with fast neutron reactors and closed fuel cycle

Calibration Experiment on the Detection of Fissioning Material in Soil by Means of Neutron Detection

Computational-Experimental Study of the Heating of Structural Materials by IGRIK Radiation

Measurement of the temperature of structural materials heated by radiation from a pulsed uranium-graphite reactor

Monitoring of the movement of a melt of fissioning material in the experimental channel of a pulsed graphite reactor igr using small neutron detectors

Increasing the Internal Protection of a Pulsed Reactor Against Wrong or Illegal Actions

Computational Investigation of the Lifetime Characteristics of IGR Neutrons

Expected Characteristics of the Multipurpose Pulsed Uranium-Graphite Reactor Complex

PRIZMA.D computational investigation of physical processes in the IGR reactor

Characteristics of the Thermal-Neutron Field in the Experimental Channel of a Pulsed Graphite Reactor

Investigation of the neutron field in the central channel of a pulse graphite reactor when the neutron absorber moves

Method for identifying 17-place casings with spent fuel assemblies of AMB reactors at the Beloyarskaya nuclear power plant

Study of the three-dimensional neutron field in the core of the IGR (pulsed graphite reactor)

Identification of the fuel parts of research reactors

A computational-experimental investigation of the temperature field of IGR masonry

Computational-Experimental Investigation of the Special Features of the Neutron Spectrum of an IGR Reactor

Dual purpose transport packaging using 'coiled' technology for treatment of spent fuel from first and second units of Beloyarskaya nuclear power plant

“Bleaching” of uranium-graphite fuel for pulse graphite reactors

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