LabCompass

Maria A. Okuniewski

Materials Science · Purdue University West Lafayette

Mid career · publishing since 2001

Publications

81

Citations

1,292

Est. group size

~5

Recurring co-author estimate

Active years

25

Publishing since 2001

Research summary
AI-generated

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.

Nuclear fuel materials (U-Zr, U-Mo alloys)Radiation damage and irradiation effects in metalsAtomic-scale diffusion and defect modelingMicrostructural characterization (electron microscopy, X-ray/neutron diffraction)Nuclear reactor cladding and structural 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

Publication cadence
Publications per year over the last 10 years — averaging 3.4/year recently
2017: 1 publication172018: 4 publications182019: 2 publications192020: 6 publications6202021: 5 publications212022: 2 publications222023: 4 publications232024: 5 publications242025: 6 publications62526
Recent publications
Publishes in
  • Journal of Nuclear Materials×16
  • MRS Advances×3
  • Acta Materialia×2
  • Computational Materials Science×2
  • Transactions American Geophysical Union×2
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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.

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