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Publications in Math-Net.Ru
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Spatial approximation of the transport equation on triangle grid by the linear discontinuous finite element method
Matem. Mod., 28:5 (2016), 81–94
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Discontinuous Finite Element Method for Solving the Transport Equation on an Unstructured Grid of Triangular Cells
Keldysh Institute preprints, 2013, 085, 24 pp.
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$\delta$-process for acceleration of outer iterations in reactor problems
Matem. Mod., 22:7 (2010), 148–160
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Reserch of stability and efficiency of space rebalance acceleration method for linear transport problems
Matem. Mod., 20:9 (2008), 75–93
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Numerical methods for solving the transport equation in multi-group approximation in three-dimensional geometry in program package “REACTOR”
Keldysh Institute preprints, 2007, 078, 22 pp.
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PARSE 3.0 — program package for three-dimensional transport calculation of neutral and charged particles by the Monte Carlo method
Keldysh Institute preprints, 2005, 126, 24 pp.
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Simulation of nuclear-physical processes in targets and blankets of hybrid systems (ADWS-systems) with the help of program package reactor
Keldysh Institute preprints, 2003, 096, 15 pp.
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PARSE 3.0 — program package for three-dimensional transport calculation of neutral and charged particles by the Monte Carlo method
Keldysh Institute preprints, 2003, 095, 22 pp.
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Neutron transport equation in the moving medium
Keldysh Institute preprints, 2001, 091
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Non-Stationary Technique for Calculation of the Multigroup Two-Dimensional Transport Equations on Grids, Formed by the Arbitrary Quadrangles
Keldysh Institute preprints, 2000, 080
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The Algorithm for Solving the Multigroup Steady-State Transport Equation for Neutrons and Gamma - Quanta on Grids, Agreed with the Structure of Calculation Domain
Keldysh Institute preprints, 2000, 079
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Calculation of a Test for Hybrid Nuclear Systems IAEA-ADS BENCHMARK with the Program Package Reactor-S
Keldysh Institute preprints, 2000, 077
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The Program Package Kinrz for Solving the Multigroup Transport Equation for Neutrons and $\gamma$- Quanta in Two-Dimensional R-Z Geometry by the Method of Discrete Ordinates
Keldysh Institute preprints, 1999, 083
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Quasistatic Approximation for Calculation of Space-Time Neutron Kinetics in Two-Dimensional R-Z Geometry
Keldysh Institute preprints, 1997, 109
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The Linear Characteristic Method of Discrete Ordinates for Solving the Transport Equation in X-Y Geometry
Keldysh Institute preprints, 1996, 091
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CDSN Method for Solving the Transport Equation in Three-Dimensional X-Y-Z Geometry
Keldysh Institute preprints, 1996, 067
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Numerical Researches of the Sodium-Void Reactivity Effect (SVR), Measured on the 'ZEBRA' Experiments
Keldysh Institute preprints, 1996, 066
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Semi-Implicit Method for Calculation of the Non-Stationary Neutron-Physical Processes in Multigroup Diffusion Approximation in Two Dimensional Geometry
Keldysh Institute preprints, 1996, 065
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Implicit Methods for Solving the Non-Stationary Transport Equation in Multygroup Diffusion Approximation in Two Dimensional Geometry
Keldysh Institute preprints, 1996, 034
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Consistent P1SA Scheme for Acceleration of Inner and Outer Iterations Convergence for the Neutron and Gamma-Rays Transport Equation in One-Dimensional Geometries: Implementation in Code Package REACTOR
Keldysh Institute preprints, 1996, 002
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Solution of the Neutron Transport Equation in R-Z and X-Y-Z Geometries by the Discrete Ordinates Method
Keldysh Institute preprints, 1995, 006
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Solution of the Diffusion Equation in R-Z Geometry by the Difference Potentials Method
Keldysh Institute preprints, 1995, 004
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