Marat Khafizov
Materials Science · The Ohio State University
Publications
153
Citations
1,993
Est. group size
~6
Recurring co-author estimate
Active years
39
Publishing since 1988
Marat Khafizov studies how nuclear fuel materials—such as uranium dioxide, uranium nitride, and thorium dioxide—behave under radiation and high temperatures, focusing on defects, thermal conductivity, and microstructural changes. The work combines experiments (like proton irradiation and electron microscopy) with computer simulations (molecular dynamics, machine learning potentials, and first-principles calculations) to predict how these materials perform in nuclear reactors. This research is aimed at understanding and improving the safety and efficiency of nuclear fuel.
Publication output has grown substantially over the last decade, rising from about 4 papers per year in 2017-2018 to a peak of 23 in 2024, with a high and roughly steady pace (around 14-16 per year) maintained through 2025-2026.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Excessive dislocation loop growth in Uranium Mononitride under high temperature proton irradiation
Scripta Materialia · 2026
- Thermal Transport in Defective Uranium Nitride: Effects of Point Defects, Anharmonicity, and Electronic Contributions
arXiv (Cornell University) · 2026
- Thermal Transport in Defective Uranium Nitride: Effects of Point Defects, Anharmonicity, and Electronic Contributions
arXiv (Cornell University) · 2026
- Oxygen interstitial-assisted cation interstitial diffusion in fluorite oxides
Acta Materialia · 2026
- Cluster Dynamics Modeling of Interstitial Loop Evolution and Loop Unfaulting in Fluorite-structured Oxide with an FCC Cation Sublattice: Case of Proton-Irradiated ThO2
SSRN Electronic Journal · 2026
- Faulted and Perfect Loop Evolution in Single Crystal Thorium Dioxide under High-Temperature Proton Irradiation
Journal of Nuclear Materials · 2025
- Parameterizing empirical interatomic potentials for predicting thermophysical properties via an irreducible derivative approach: the case of ThO<sub>2</sub> and UO<sub>2</sub>
Journal of Physics Condensed Matter · 2025
- Machine learning interatomic potential for predicting the thermal properties of uranium nitride
Journal of Applied Physics · 2025
- Implications of point defect accumulation on UO2 thermal conductivity and fission gas release under accelerated fuel irradiation
Journal of Nuclear Materials · 2025
- Integrated multiscale experiment and model analysis of radially resolved microstructure and thermal conductivity in mixed oxide fuel
Journal of Nuclear Materials · 2025
- Implications of Point Defect Accumulation on Uo2 Thermal Conductivity and Fission Gas Release Under Accelerated Fuel Irradiation
SSRN Electronic Journal · 2025
- Experimental confirmation of first-principles thermal conductivity in Zirconium-doped ThO2
Journal of Nuclear Materials · 2025
- Anomalous ionic conductivity along the coherent Σ3 grain boundary in ThO2
Scripta Materialia · 2025
- Anomalous Ionic Conductivity along the Coherent $Σ$3 Grain Boundary in ThO2
arXiv (Cornell University) · 2025
- Machine learning interatomic potential for predicting the thermal properties of uranium nitride
arXiv (Cornell University) · 2025
- Journal of Nuclear Materials×16
- arXiv (Cornell University)×16
- SSRN Electronic Journal×10
- Journal of Applied Physics×8
- Acta Materialia×7
- Saqeeb Adnan
Materials Science · The Ohio State University
- Yi Xie
Materials Science · Purdue University West Lafayette
- W. Ryan Deskins
Materials Science · Purdue University West Lafayette
- Ketan Ajay
Materials Science · Purdue University West Lafayette
- Logan Joyce
Materials Science · Purdue University West Lafayette
This profile was generated automatically from public scholarly data (OpenAlex). Group size and activity levels are estimates derived from co-authorship patterns.
Last updated Jul 19, 2026.
Claim or correct this profile