Maria A. Okuniewski
Materials Science · Purdue University West Lafayette
Publications
81
Citations
1,292
Est. group size
~5
Recurring co-author estimate
Active years
25
Publishing since 2001
Maria A. Okuniewski studies nuclear fuel and reactor materials, particularly uranium-based alloys (such as U-Zr and U-Mo) used in nuclear fuel, examining how their structure changes under irradiation and heat. Her work combines experimental microscopy and diffraction techniques with computational modeling to understand atomic-scale processes like diffusion, phase transformations, and defect behavior in these materials. This research supports the development of safer and more durable nuclear reactor fuels and materials.
Publication output has been fairly steady with some year-to-year fluctuation, showing a modest upward trend in the most recent years (2023–2025) after a dip around 2022.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- First-principles investigation of cerium and neodymium diffusion in BCC chromium and vanadium via vacancy-mediated transport
Journal of Nuclear Materials · 2025
- First-principles investigation of lanthanides diffusion in HCP zirconium via vacancy-mediated transport
Journal of Nuclear Materials · 2024
- Residual stresses in aluminum clad uranium-10 weight%molybdenium fuel plates
OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2024
- Transmission electron microscopy investigation of phase transformation and fuel constituent redistribution in neutron irradiated U-10wt.%Zr fuel
Journal of Nuclear Materials · 2023
- Phase transformations and thermal expansion coefficients of unirradiated U-X wt.% Zr (X = 6, 10, 20, 30) measured via neutron diffraction
Journal of Nuclear Materials · 2023
- 3-D reconstruction and microstructural characterization of neutron-irradiated U-10Zr fuel using FIB-SEM serial sectioning
MRS Advances · 2023
- Computational determination of a primary diffusion mode in <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si1.svg"><mml:mi>γ</mml:mi></mml:math>U-10Mo under irradiation
Journal of Nuclear Materials · 2022
- An atomistic study of defect energetics and diffusion with respect to composition and temperature in <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si1.svg"><mml:mi>γ</mml:mi></mml:math>U and <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" altimg="si1.svg"><mml:mi>γ</mml:mi></mml:math>U-Mo alloys
Journal of Nuclear Materials · 2021
- Phase identification and morphology in rolled and annealed U-22.5at.%Zr foils
MRS Advances · 2021
- Nano-mechanical property assessment of a neutron-irradiated HT-9 steel cladding and a fuel-cladding chemical interaction region of a uranium–10 wt% zirconium nuclear fuel
MRS Advances · 2021
- Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation
Journal of Nuclear Materials · 2021
- Microstructural-Level Fuel Performance Modeling of U-Mo Monolithic Fuel
2021
- In Situ Neutron Diffraction Study of Crystallographic Evolution and Thermal Expansion Coefficients in U-22.5 at.%Zr During Annealing
JOM · 2020
- A Novel In-situ Creep Capsule Design for the Versatile Test Reactor
Transactions of the American Nuclear Society - Volume 123 · 2020
- Assessment of swelling and constituent redistribution in uranium-zirconium fuel using phenomena identification and ranking tables (PIRT)
Annals of Nuclear Energy · 2019
- Journal of Nuclear Materials×16
- MRS Advances×3
- Acta Materialia×2
- Computational Materials Science×2
- Transactions American Geophysical Union×2
- Jian Gan
Materials Science · Purdue University West Lafayette
- Brandon Miller
Materials Science · Purdue University West Lafayette
- Md Ali Muntaha
Materials Science · Purdue University West Lafayette
- Haozheng J. Qu
Materials Science · Purdue University West Lafayette
- Sanjoy Mazumder
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 20, 2026.
Claim or correct this profile