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Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data

Atomic energy (New York, N.Y.), 2023-03, Vol.133 (5-6), p.288-291

2023

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Development and testing of algorithms for performing computation of detector readings from a pulsed neutron source

Journal of physics. Conference series, 2020-11, Vol.1689 (1), p.12055

2020

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Overview of the MCU Monte Carlo software package

Annals of nuclear energy, 2015-08, Vol.82, p.54-62

2015

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Neutron-Value Function Influence on the Accuracy of MCU-Aided Calculations of the Effective Delayed-Neutron Fraction and Prompt-Neutron Generation Time: An Investigation

Atomic energy (New York, N.Y.), 2022-09, Vol.132 (5), p.272-276

2022

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MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor

Atomic energy (New York, N.Y.), 2022-09, Vol.132 (5), p.277-281

2022

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Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code

Journal of nuclear engineering and radiation science, 2022-04, Vol.8 (2)

2022

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On a Strategy for the Development of Nuclear Power in Russia

Atomic energy (New York, N.Y.), 2019-08, Vol.126 (4), p.207-212

2019

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Evaluation of the systematic error of Monte Carlo calculations of neutron-physical properties using a multiprocessor computer

Atomic energy (New York, N.Y.), 2011-12, Vol.111 (2), p.79-85

2011

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MCU Code Precision Calculation of the Power Release in a VVER-1000 Core at Nominal Power Taking Feedbacks into Account

Atomic energy (New York, N.Y.), 2013-09, Vol.114 (5), p.315-317

2013

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Monte Carlo calculation of the diffusion coefficient of nuclear reactor cells

Atomic energy (New York, N.Y.), 2009-04, Vol.106 (4), p.231-237

2009

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Estimation of some neutron physics characteristics by Monte-Carlo method using the importance function

Annals of nuclear energy, 2019-08, Vol.130, p.388-393

2019

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Numerical simulation of mixed oxide fuel burnup taking account of double heterogeneity

Atomic energy (New York, N.Y.), 2009, Vol.106 (1), p.33-36

2009

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Applying full multigroup cell characteristics from MCU code to finite difference calculations of neutron field in VVER core

Kerntechnik (1987), 2015-08, Vol.80 (4), p.321-325

2015

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MCU-FCP program for first-collisions probability calculations of neutron transport

Atomic energy (New York, N.Y.), 2008-08, Vol.105 (2), p.84-89

2008

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Simulation of the radiation fields from ionizing radiation sources inside the containment in an accident

Physics of atomic nuclei, 2010-12, Vol.73 (13), p.2198-2202

Kalugin, M. A.

2010

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Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code

Kerntechnik (1987), 2018-08, Vol.83 (4), p.299-306

2018

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Validation of the correctness of the Hald approximation in assessing tolerance

Physics of atomic nuclei, 2014-12, Vol.77 (13), p.1559-1562

2014

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Development of codes and KASKAD complex

Kerntechnik (1987), 2015-08, Vol.80 (4), p.314-320

2015

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The status of MCU-5

Physics of atomic nuclei, 2012-12, Vol.75 (14), p.1634-1646

2012

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The estimation techniques of the time series correlations in nuclear reactor calculations by the Monte Carlo method using multiprocessor computers

Physics of atomic nuclei, 2012-12, Vol.75 (14), p.1669-1674

2012

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Verification of the MCU precision code and ROSFOND neutron data in application to the calculations of criticality of fast reactors with highly enriched uranium

Physics of atomic nuclei, 2014-12, Vol.77 (13), p.1583-1590

2014

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Statistical error of reactor calculations by the Monte Carlo method

Physics of atomic nuclei, 2011-12, Vol.74 (14), p.1871-1877

2011

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Comparison of computational results obtained for critical assemblies with MCU-RFFI and MCNP codes

Atomic energy (New York, N.Y.), 1997-09, Vol.83 (3), p.633-637

1997

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Development of multi-group spectral code TVS-M

Kerntechnik (1987), 2012-08, Vol.77 (4), p.213-217

2012

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A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor

Annals of nuclear energy, 2006-05, Vol.33 (8), p.739-748

2006

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Study of the Sensitivity of the Calculated Radiation Load on VVER-1000 Internals to the Uncertainty of Initial Data

Development and testing of algorithms for performing computation of detector readings from a pulsed neutron source

Overview of the MCU Monte Carlo software package

Neutron-Value Function Influence on the Accuracy of MCU-Aided Calculations of the Effective Delayed-Neutron Fraction and Prompt-Neutron Generation Time: An Investigation

MCU–RELAP Software Package for Analyzing Accidents and Non-Stationary Processes in the PIK Reactor

Using the Few-Group Approximation for Calculating Some Neutron-Physical Characteristics of VVER-1000 Core by Means of the Monte Carlo Universal Code

On a Strategy for the Development of Nuclear Power in Russia

Evaluation of the systematic error of Monte Carlo calculations of neutron-physical properties using a multiprocessor computer

MCU Code Precision Calculation of the Power Release in a VVER-1000 Core at Nominal Power Taking Feedbacks into Account

Monte Carlo calculation of the diffusion coefficient of nuclear reactor cells

Estimation of some neutron physics characteristics by Monte-Carlo method using the importance function

Numerical simulation of mixed oxide fuel burnup taking account of double heterogeneity

Applying full multigroup cell characteristics from MCU code to finite difference calculations of neutron field in VVER core

MCU-FCP program for first-collisions probability calculations of neutron transport

Simulation of the radiation fields from ionizing radiation sources inside the containment in an accident

Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code

Validation of the correctness of the Hald approximation in assessing tolerance

Development of codes and KASKAD complex

The status of MCU-5

The estimation techniques of the time series correlations in nuclear reactor calculations by the Monte Carlo method using multiprocessor computers

Verification of the MCU precision code and ROSFOND neutron data in application to the calculations of criticality of fast reactors with highly enriched uranium

Statistical error of reactor calculations by the Monte Carlo method

Comparison of computational results obtained for critical assemblies with MCU-RFFI and MCNP codes

Development of multi-group spectral code TVS-M

A benchmark on the calculation of kinetic parameters based on reactivity effect experiments in the CROCUS reactor

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