Dmitriy Anistratov

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

A Variable Eddington Factor Model for Thermal Radiative Transfer with Closure Based on Data-Driven Shape Function
Coale, J. M., & Anistratov, D. Y. (2024, March 11), JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT. https://doi.org/10.1080/23324309.2024.2327992
A reduced-order model for nonlinear radiative transfer problems based on moment equations and POD-Petrov-Galerkin projection of the normalized Boltzmann transport equation
Coale, J. M., & Anistratov, D. Y. (2024), JOURNAL OF COMPUTATIONAL PHYSICS, 509. https://doi.org/10.1016/j.jcp.2024.113044
Accelerated Deterministic Phonon Transport With Consistent Material Temperature and Intensities
Whitman, N. H., Palmer, T. S., Anistratov, D. Y., & Greaney, P. A. (2023), ASME JOURNAL OF HEAT AND MASS TRANSFER, 145(1). https://doi.org/10.1115/1.4056140
Foreword Selected papers from the 2021 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering ( M&C 2021)
Brantley, P. S., Anistratov, D. Y., & Urbatsch, T. J. (2023, February 1), NUCLEAR SCIENCE AND ENGINEERING, Vol. 197, pp. III-IV. https://doi.org/10.1080/00295639.2022.2157619
Re duce d order models for thermal radiative transfer problems based on moment equations and data-driven approximations of the Eddington tensor
Coale, J. M., & Anistratov, D. Y. (2023), JOURNAL OF QUANTITATIVE SPECTROSCOPY & RADIATIVE TRANSFER, 296. https://doi.org/10.1016/j.jqsrt.2022.108458
Nonlinear iterative projection methods with multigrid in photon frequency for thermal radiative transfer
Anistratov, D. Y. (2021), JOURNAL OF COMPUTATIONAL PHYSICS, 444. https://doi.org/10.1016/j.jcp.2021.110568
An Approximation Method for Time-Dependent Problems in High Energy Density Thermal Radiative Transfer
Ghassemi, P., & Anistratov, D. Y. (2020), JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT, 49(1), 31–50. https://doi.org/10.1080/23324309.2019.1709082
Multilevel quasidiffusion method with mixed-order time discretization for multigroup thermal radiative transfer problems
Ghassemi, P., & Anistratov, D. Y. (2020), JOURNAL OF COMPUTATIONAL PHYSICS, 409. https://doi.org/10.1016/j.jcp.2020.109315
Iteration Methods with Multigrid in Energy for Eigenvalue Neutron Diffusion Problems
Cornejo, L. R., Anistratov, D. Y., & Smith, K. (2019), NUCLEAR SCIENCE AND ENGINEERING, 193(8), 803–827. https://doi.org/10.1080/00295639.2019.1573601
Stability analysis of a multilevel quasidiffusion method for thermal radiative transfer problems
Anistratov, D. Y. (2019), JOURNAL OF COMPUTATIONAL PHYSICS, 376, 186–209. https://doi.org/10.1016/j.jcp.2018.09.034

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Grants

CEMeNT: Center for Exascale Monte Carlo Neutron Transport - A PSAAP - III Focused Investigatory Center
US Dept. of Energy (DOE)(9/30/20 - 9/29/25)
Capsaicin Modernization Project
US Dept. of Energy (DOE)(4/15/22 - 4/30/24)
Reduced-Order Models for Radiation-Hydrodynamics Problems
Sandia National Laboratories(12/16/20 - 9/30/23)
Model Order Reduction Approaches to Radiation Hydrodynamics with Application to Nuclear Weapons Effects Simulations (ID: HDTRA1-1-14-24-FRCWMD-BAA)
Defense Threat Reduction Agency (DTRA)(6/20/18 - 6/30/22)
Consortium for Advanced Simulations for Light Water Reactors (CASL) - Oak Ridge National laboratory (Start up 8/16/10 to 2/17/11)
US Dept. of Energy (DOE)(11/16/10 - 12/01/20)
Project Title: Analysis 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)
Nonlinear Accelaration Methods For Solving Multigroup Neutron Diffusion Equations
Battelle Energy Alliance, LLC(7/08/08 - 8/17/08)
Project Title: Analysis of Curvilinear Geometry Characteristic- Based Particle Transport Discretizations
US Dept. of Energy (DOE)(9/21/06 - 10/31/07)