Dmitriy Anistratov
Professor of Nuclear Engineering

- 919-513-4353
- anistratov@ncsu.edu
- Burlington Laboratory 2105
- Visit My Website
Education
Mathematical and Physical Sciences
Institute for Mathematical Modeling, Russian Academy of Sciences
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
- 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
- Discontinuous Finite Element Quasi-Diffusion Methods
- Anistratov, D. Y., & Warsa, J. S. (2018), NUCLEAR SCIENCE AND ENGINEERING, 191(2), 105–120. https://doi.org/10.1080/00295639.2018.1450013
- Two-Level Transport Methods with Independent Discretization
- Warsa, J. S., & Anistratov, D. Y. (2018), JOURNAL OF COMPUTATIONAL AND THEORETICAL TRANSPORT, 47(4-6), 424–450. https://doi.org/10.1080/23324309.2018.1497991
Grants
- Capsaicin Modernization Project
- US Dept. of Energy (DOE)(4/15/22 - 4/30/24)
- Reduced-Order Models for Radiation-Hydrodynamics Problems
- National Technology and Engineering Solutions of Sandia, LLC. (Sandia National Laboratories) (12/16/20 - 9/30/23)
- CEMeNT: Center for Exascale Monte Carlo Neutron Transport
- US Dept. of Energy (DOE)(9/30/20 - 9/29/23)
- 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
- US Dept. of Energy (DOE)(11/16/10 - 12/01/20)
- 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)