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Publications in Math-Net.Ru

  1. Spatial approximation of the transport equation on triangle grid by the linear discontinuous finite element method

    Matem. Mod., 28:5 (2016),  81–94
  2. Discontinuous Finite Element Method for Solving the Transport Equation on an Unstructured Grid of Triangular Cells

    Keldysh Institute preprints, 2013, 085, 24 pp.
  3. $\delta$-process for acceleration of outer iterations in reactor problems

    Matem. Mod., 22:7 (2010),  148–160
  4. Reserch of stability and efficiency of space rebalance acceleration method for linear transport problems

    Matem. Mod., 20:9 (2008),  75–93
  5. 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.
  6. 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.
  7. 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.
  8. 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.
  9. Neutron transport equation in the moving medium

    Keldysh Institute preprints, 2001, 091
  10. Non-Stationary Technique for Calculation of the Multigroup Two-Dimensional Transport Equations on Grids, Formed by the Arbitrary Quadrangles

    Keldysh Institute preprints, 2000, 080
  11. 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
  12. Calculation of a Test for Hybrid Nuclear Systems IAEA-ADS BENCHMARK with the Program Package Reactor-S

    Keldysh Institute preprints, 2000, 077
  13. 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
  14. Quasistatic Approximation for Calculation of Space-Time Neutron Kinetics in Two-Dimensional R-Z Geometry

    Keldysh Institute preprints, 1997, 109
  15. The Linear Characteristic Method of Discrete Ordinates for Solving the Transport Equation in X-Y Geometry

    Keldysh Institute preprints, 1996, 091
  16. CDSN Method for Solving the Transport Equation in Three-Dimensional X-Y-Z Geometry

    Keldysh Institute preprints, 1996, 067
  17. Numerical Researches of the Sodium-Void Reactivity Effect (SVR), Measured on the 'ZEBRA' Experiments

    Keldysh Institute preprints, 1996, 066
  18. 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
  19. Implicit Methods for Solving the Non-Stationary Transport Equation in Multygroup Diffusion Approximation in Two Dimensional Geometry

    Keldysh Institute preprints, 1996, 034
  20. 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
  21. Solution of the Neutron Transport Equation in R-Z and X-Y-Z Geometries by the Discrete Ordinates Method

    Keldysh Institute preprints, 1995, 006
  22. Solution of the Diffusion Equation in R-Z Geometry by the Difference Potentials Method

    Keldysh Institute preprints, 1995, 004


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