Lauren Garrison

Profile Information
Name
Dr. Lauren Garrison
Institution
Oak Ridge National Laboratory
Publications:
"Evaluation of Zircaloy-4 Welding and Hydrogen Charging Effects for Use as the Structural Material for the Target Solution Vessel and Support Lines of SHINE" Lauren Garrison, Chinthaka Silva, Brian Eckhart, Chris Bryan, ORNL Report Vol. TM-2018/1035 2018 1-23
N/A
"Microstructural evolution of pure tungsten neutron irradiated with a mixed energy spectrum" Lauren Garrison, Yutai Katoh, Takaaki Koyanagi, Lance Snead, Kiran Kumar, Taehyun Hwang, Xunxiang Hu, Journal of Nuclear Materials Vol. 490 2017 66-74 Link
Microstructures of single-crystal bulk tungsten (W) and polycrystalline W foil with a strong grain texture were investigated using transmission electron microscopy following neutron irradiation at ∼90–800 °C to 0.03–4.6 displacements per atom (dpa) in the High Flux Isotope Reactor with a mixed energy spectrum. The dominant irradiation defects were dislocation loops and small clusters at ∼90 °C. Additional voids were formed in W irradiated at above 460 °C. Voids and precipitates involving transmutation rhenium and osmium were the dominant defects at more than ∼1 dpa. We found a new phenomenon of microstructural evolution in irradiated polycrystalline W: Re- and Os-rich precipitation along grain boundaries. Comparison of results between this study and previous studies using different irradiation facilities revealed that the microstructural evolution of pure W is highly dependent on the neutron energy spectrum in addition to the irradiation temperature and dose.
"Surface morphologies of He-implanted tungsten" Lauren Garrison, Chad Parish, Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms Vol. 382 2016 76-81 Link