Dmitriy Anistratov

Associate Professor of Nuclear Engineering

Education

Ph.D. 1993

Mathematical and Physical Sciences

Institute for Mathematical Modeling, Russian Academy of Sciences

M.S. 1985

Physics

Moscow Institute of Physics and Technology

Research Description

Dr. Anistratov works in the field of computational physics, transport theory and numerical analysis. His research interests involve numerical methods for solving particle transport and radiative transfer problems. These kinds of problems arise in such areas as reactor physics, astrophysics, medical physics, geophysics and atmospheric sciences. His research includes development and analysis of iteration methods for the transport equation, discretization methods for partial differential equations, methods for solving transport equation coupled with equations of matter, and mathematical models of transport process in various physical systems.

Publications

Stability analysis of nonlinear two-grid method for multigroup neutron diffusion problems
Anistratov, D. Y., Cornejo, L. R., & Jones, J. P. (2017), Journal of Computational Physics, 346, 278-294.
Sensitivity analysis of neutron multiplicity counting statistics using first-order perturbation theory and application to a subcritical plutonium metal benchmark
O'Brien, S., Mattingly, J., & Anistratov, D. (2017), Nuclear Science and Engineering, 185(3), 406-425.
Nonlinear diffusion acceleration method with multigrid in energy for k-eigenvalue neutron transport problems
Cornejo, L. R., & Anistratov, D. Y. (2016), Nuclear Science and Engineering, 184(4), 514-526.
Space-angle homogenization of the step characteristic scheme
Anistratov, D. Y., & Jones, J. P. (2015), Transport Theory and Statistical Physics, 44(4-5), 215-228.
Iterative stability analysis of spatial domain decomposition based on block Jacobi algorithm for the diamond-difference scheme
Anistratov, D. Y., & Azmy, Y. Y. (2015), Journal of Computational Physics, 297, 462-479.
Spatial homogenization of transport discretization schemes
Anistratov, D., & Jones, J. (2014), Transport Theory and Statistical Physics, 43(1-7), 262-288.
A cell-local finite difference discretization of the low-order quasidiffusion equations for neutral particle transport on unstructured quadrilateral meshes
Wieselquist, W. A., Anistratov, D. Y., & Morel, J. E. (2014), Journal of Computational Physics, 273, 343-357.
A hybrid transport-diffusion method for 2D transport problems with diffusive subdomains
Stehle, N. D., Anistratov, D. Y., & Adams, M. L. (2014), Journal of Computational Physics, 270, 325-344.
A Multilevel projective method for solving the space-time multigroup neutron kinetics equations coupled with the heat transfer equation
Tamang, A., & Anistratov, D. Y. (2014), Nuclear Science and Engineering, 177(1), 1-18.
Multilevel NDA methods for solving multigroup eigenvalue neutron transport problems
Anistratov, D. Y. (2013), Nuclear Science and Engineering, 174(2), 150-162.

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Grants

Consortium for Advanced Simulations for Light Water Reactors (CASL) - Oak Ridge National laboratory
US Dept. of Energy (DOE)(11/30/-1 - 9/30/19)
Nonlinear Accelaration Methods For Solving Multigroup Neutron Diffusion Equations
Battelle Energy Alliance, LLC(7/08/08 - 8/17/08)
Analysis and Development of Curvilinear Geometry Characteristic-Based Particle Transport Discretizations
US Dept. of Energy (DOE)(11/09/07 - 12/31/09)
Enhancement of Computational Facilities in Support of GNEP Research and Training
US Dept. of Energy (DOE)(9/01/07 - 8/31/08)
Project Title: Analysis of Curvilinear Geometry Characteristic- Based Particle Transport Discretizations
US Dept. of Energy (DOE)(9/21/06 - 10/31/07)