Laura Hawkins
Materials Science · Purdue University West Lafayette
Publications
23
Citations
295
Est. group size
~2
Recurring co-author estimate
Active years
35
Publishing since 1991
Laura Hawkins studies how materials used in nuclear and fusion reactors behave when exposed to radiation, high temperatures, and corrosive environments like molten salts. Her work combines ion/proton irradiation experiments with microscopy-based mechanical testing (such as micro-pillar compression and in-situ testing inside electron microscopes) to understand how radiation damage changes the strength and fracture behavior of metals and alloys. This research supports the design of safer, more durable materials for advanced nuclear reactors.
Publication output began around 2021 and has remained fairly steady since, averaging about 3-5 papers per year through 2025.
Generated by claude-sonnet-5 from public bibliographic data · Jul 20, 2026
- Radiobiological characterisation of a 28 MeV proton beam delivered by the MC-40 cyclotron
Cell Death Discovery · 2025
- Corrosion Response of Ni-19Cr-5Fe in Molten NaCl-MgCl2 Salt
JOM · 2025
- Finite element analysis of the impact of beam heating mode in molten salt corrosion experiments employing simultaneous ion irradiation
Nuclear Instruments and Methods in Physics Research Section B Beam Interactions with Materials and Atoms · 2025
- Fracture behavior of irradiation induced nanocrystalline UO2 studied by in-situ mechanical testing in transmission electron microscopy
Journal of Nuclear Materials · 2024
- Micro-pillar compression of proton-irradiated chromium examined using cross-sectional site selection, electron microscopy, and molecular dynamics simulation
Journal of Nuclear Materials · 2024
- In-Plane Liftout and Push-to-Pull for In Situ Mechanical Testing of Irradiated Inconel X-750
Energies · 2024
- A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals
Journal of Nuclear Materials · 2022
- Effect of dpa rate on the temperature regime of void swelling in ion-irradiated pure chromium
Journal of Nuclear Materials · 2022
- Measurement of grain boundary strength of Inconel X-750 superalloy using in-situ micro-tensile testing techniques in FIB/SEM system
Materials Science and Engineering A · 2022
- Microstructural changes of proton irradiated Hastelloy-N and in situ micropillar compression testing of one single grain at different local damage levels
Journal of Nuclear Materials · 2022
- ZrN Phase Formation, Hardening and Nitrogen Diffusion Kinetics in Plasma Nitrided Zircaloy-4
Materials · 2021
- Journal of Nuclear Materials×10
- Microscopy and Microanalysis×2
- Acta Materialia×1
- Corrosion Science×1
- Materials Science and Engineering A×1
- Jian Gan
Materials Science · Purdue University West Lafayette
- Haozheng J. Qu
Materials Science · Purdue University West Lafayette
- Maria A. Okuniewski
Materials Science · Purdue University West Lafayette
- Brandon Miller
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 20, 2026.
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