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GEANT4 Simulation of the High-Energy Neutron Beam of the TOF Spectrometer GNEIS
Nakin A., Vorobyev A., Shcherbakov O.
Calculation of Prompt Fission Neutron Lifetimes by the Monte Carlo Method
Gomin E., Davidenko V., Zinchenko A., Kharchenko I.
Monte Carlo Simulation of Neutronic Characteristics of the Yalina-Thermal Subcritical Assembly Using the ENDF/B-VII and JENDL-3.2 Evaluated Neutron Data Libraries
Beresneva V., Korbut T., Korneyev S.
Application of the Monte Carlo method for spectrometer calibration to determine the surface activity of radionuclides deposited on the ground
Finkel F., Rebyakova V., Spirin D.
Criticality calculation of non-ordinary systems
Kalugin A., Tebin V.
Argus Solution Reactor Nuclear Safety Validation Using the DAREUS Software Package
Gomin E., Davidenko V., Davidenko O., Kovalishin A., Laletin M., Myasnikov S., Pavlov A., Pavshuk V., Petrunin N.
Time-dependent integral equations of neutron transport for calculating the kinetics of nuclear reactors by the Monte Carlo method
Davidenko V., Zinchenko A., Harchenko I.
DAREUS Software Package for Modeling the Dynamics of Solution Reactors Using the Monte Carlo Method
Gomin E., Davidenko V., Davidenko O., Kovalishin A., Laletin M., Pavlov A.
Simulation of Nuclear Reactor Kinetics by the Monte Carlo Method
Gomin E., Davidenko V., Zinchenko A., Kharchenko I.
Calculation of the Neutron Importance Function and the Delayed Neutron Effective Fraction by the Monte Carlo Method
Gomin E., Davidenko V., Zinchenko A., Kharchenko I.
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