LabCompass

Md Ali Muntaha

Materials Science · Purdue University West Lafayette

OpenAlex ORCID
Mid career · publishing since 2016Rising activity
Nuclear Materials and PropertiesNuclear reactor physics and engineeringRadioactive element chemistry and processingFusion materials and technologiesNuclear Physics and Applications

Publications

13

Citations

54

Est. group size

—

Recurring co-author estimate

Active years

11

Publishing since 2016

Research summary
AI-generated

Md Ali Muntaha works on modeling nuclear fuel materials, particularly uranium dioxide (UO2), focusing on how radiation exposure causes microscopic changes like grain growth and the release of fission gas bubbles. This research uses computational and multiscale simulation methods, including machine learning techniques, to predict how nuclear fuel behaves and degrades under reactor conditions.

Nuclear fuel performance modelingFission gas release and bubble behaviorGrain growth under irradiationMultiscale computational simulationMachine learning for materials modeling

Publication output was minimal or absent from 2017-2022 but has grown noticeably from 2023 through 2025-2026, suggesting an increasing and recent research pace.

Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026

Publication cadence
Publications per year over the last 10 years — averaging 2.0/year recently
172018: 1 publication1819202021: 1 publication21222023: 2 publications232024: 4 publications4242025: 3 publications252026: 1 publication26
Recent publications
Publishes in
  • Journal of Nuclear Materials×3
  • Corrosion Science×2
  • AIP conference proceedings×2
  • arXiv (Cornell University)×2
  • SSRN Electronic Journal×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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