Janelle P. Wharry
Materials Science · Purdue University West Lafayette
Publications
224
Citations
2,429
Est. group size
~14
Recurring co-author estimate
Active years
17
Publishing since 2010
Janelle P. Wharry's research focuses on how nuclear materials—especially steels and other metal alloys used in reactors—behave and degrade under radiation exposure and mechanical stress. Her work combines microscopy and nanoscale mechanical testing to understand irradiation damage, welding effects, and phase changes in materials, aiming to improve the safety and durability of nuclear reactor components. This work spans fundamental materials science and applied nuclear engineering, often in collaboration with national laboratories.
Publication output has fluctuated over the past decade with a notable spike in 2018 and again in 2026, alongside a steady baseline of activity in most other years, averaging about 22 publications per year over the last five years.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Developing in-situ Diagnostics for Evaluation of Incipient Electrochemical Nucleation and Growth
ECS Meeting Abstracts · 2026
- Linear complexions enable unprecedented ductility retention in neutron irradiated ferritic steel
Nature Communications · 2026
- Irradiation Tailoring of Deformation-Induced Phase Transformations
2026
- Nanoindentation Orientation and Solute-Influenced Deformation Mechanisms in Irradiated bcc Fe Binary Alloys
JOM · 2026
- BOILER Experiment Material Characterization and HFIR Irradiation Status
2025
- Dataset of scanning electron microscopy and nanoindentation profiles across electron beam welded SA508 Grade 3 Class 1 steel
Data in Brief · 2025
- Linear complexions enable unprecedented ductility retention in neutron irradiated ferritic steel
Research Square · 2025
- Structure-property relationships in electron beam welded SA508 nuclear reactor pressure vessel steel
International Journal of Pressure Vessels and Piping · 2025
- Irradiation-assisted pseudoelasticity in 316L stainless steel through dislocation loop-controlled martensitic phase transformations
Materials Research Letters · 2025
- Structure-Property Relationships in Electron Beam Welded Sa508 Nuclear Reactor Pressure Vessel Steel
SSRN Electronic Journal · 2025
- Applying to Graduate School: Tips & Tricks
JOM · 2025
- Nuclear Reactor Pressure Vessel Welds: A Critical and Historical Review of Microstructures, Mechanical Properties, Irradiation Effects, and Future Opportunities
Materials & Design · 2024
- Enhanced Radiation Damage Tolerance of Amorphous Interphase and Grain Boundary Complexions in Cu-Ta
JOM · 2024
- Observations of the irradiation hardening behavior in neutron irradiated HT-9 steels through in situ TEM nano-mechanical tests
Journal of Nuclear Materials · 2024
- Basic Energy Sciences Roundtable: Foundational Science to Accelerate Nuclear Energy Innovation
2024
- Boise State Data Sets×41
- DOE Idaho National Laboratory (INL) Repository×37
- Journal of Nuclear Materials×20
- JOM×12
- SSRN Electronic Journal×10
- Caleb D. Clement
Materials Science · Purdue University West Lafayette
- Ye Yuan
Materials Science · Purdue University West Lafayette
- A. Hassanein
Materials Science · Purdue University West Lafayette
- Patrick H. Warren
Materials Science · Purdue University West Lafayette
- J. Tripathi
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