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Benjamin Maier

Observed names: B. Maier, B. R. Maier, B.R Maier, B.R. Maier, Ben Maier, Benjamin R. Maier
ORCID: 0000-0003-0304-9128
Observed ORCID: 0000-0003-0304-9128
OpenAlex ID: A5034023116
High temperature oxidation and microstructural evolution of cold spray chromium coatings on Zircaloy-4 in steam environments
2019 · Hwasung Yeom, Benjamin Maier, et al. · Journal of Nuclear Materials · 249
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Cold spray deposition of Ti2AlC coatings for improved nuclear fuel cladding
2015 · Benjamin R. Maier, Brenda L. Garcia-Diaz, et al. · Journal of Nuclear Materials · 185
Development of cold spray chromium coatings for improved accident tolerant zirconium-alloy cladding
2019 · Benjamin Maier, Hwasung Yeom, et al. · Journal of Nuclear Materials · 140
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Development of cold spray process for oxidation-resistant FeCrAl and Mo diffusion barrier coatings on optimized ZIRLO™
2018 · Hwasung Yeom, Benjamin Maier, et al. · Journal of Nuclear Materials · 95
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Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors
2017 · Benjamin Maier, Hwasung Yeom, et al. · JOM · 92
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Experimental evaluation of cold spray FeCrAl alloys coated zirconium-alloy for potential accident tolerant fuel cladding
2019 · Tyler Dabney, Greg Johnson, et al. · Nuclear Materials and Energy · 81
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Magnetron sputter deposition of zirconium-silicide coating for mitigating high temperature oxidation of zirconium-alloy
2017 · Hwasung Yeom, Benjamin Maier, et al. · Surface and Coatings Technology · 53
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In situ TEM investigation of irradiation-induced defect formation in cold spray Cr coatings for accident tolerant fuel applications
2018 · Benjamin R. Maier, Hwasung Yeom, et al. · Journal of Nuclear Materials · 49
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Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding
2019 · Jonathan G. Gigax, Miltiadis Kennas, et al. · Journal of Nuclear Materials · 48
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Interface reactions and mechanical properties of FeCrAl-coated Zircaloy-4
2019 · Jonathan G. Gigax, Miltiadis Kennas, et al. · Journal of Nuclear Materials · 38
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Improving deposition efficiency in cold spraying chromium coatings by powder annealing
2018 · Hwasung Yeom, Tyler Dabney, et al. · The International Journal of Advanced Manufacturing Technology · 38
Evolution of multilayered scale structures during high temperature oxidation of ZrSi2
2016 · Hwasung Yeom, Ben Maier, et al. · Journal of materials research/Pratt's guide to venture capital sources · 33
High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer
2023 · Hwasung Yeom, Greg Johnson, et al. · Journal of Nuclear Materials · 30
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Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings by coupling digital image correlation and acoustic emission
2019 · David C. Roache, Alex Jarama, et al. · Materials Science and Engineering A · 28
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A novel approach for manufacturing oxide dispersion strengthened (ODS) steel cladding tubes using cold spray technology
2019 · Benjamin Maier, Mia Lenling, et al. · Nuclear Engineering and Technology · 24
Irradiation-induced effects of proton irradiation on zirconium carbides with different stoichiometries
2014 · Y. Huang, B.R. Maier, et al. · Nuclear Engineering and Design · 24
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Manufacturing Oxide Dispersion-Strengthened (ODS) Steel Fuel Cladding Tubes Using the Cold Spray Process
2019 · Mia Lenling, Hwasung Yeom, et al. · JOM · 22
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Unveiling damage mechanisms of chromium-coated zirconium-based fuel claddings at LWR operating temperature by in-situ digital image correlation
2021 · David C. Roache, Clifton H. Bumgardner, et al. · Surface and Coatings Technology · 17
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In situ X-ray computed micro-tomography imaging of failure processes in Cr-coated Zircaloy nuclear fuel cladding materials
2023 · Guanjie Yuan, J. Paul Forna-Kreutzer, et al. · Materials & Design · 13
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Radiation response of FeCrAl-coated Zircaloy-4
2020 · Miltiadis Kennas, Hyosim Kim, et al. · Journal of Nuclear Materials · 12
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Time in DNB experimental study on Cr coated zircaloy cladding
2024 · Tiago A. Moreira, Keegan D. Murray, et al. · Applied Thermal Engineering · 10
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Enhancing Crack Detection in Critical Structures Using Machine Learning and 3D Digital Image Correlation
2024 · O. Holzmond, D.C. Roache, et al. · Experimental Mechanics · 8
University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis
2013 · K. G. Field, C. J. Wetteland, et al. · AIP conference proceedings · 7
Silver diffusivity measurement in ZrC with SIMS to study the release behavior of 110mAg for nuclear fuel applications
2016 · Benjamin Maier, Young-Ki Yang, et al. · Journal of Nuclear Materials · 6
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Comparison of Internal Stresses and Oxidation Induced by Quenching of Cr-Coated and Uncoated Optimized Zirlo™ Part Ii: Stress Assessment
2023 · Diana Elizabeth Burden, Timothy Michael Harrell, et al. · Journal of Alloys and Compounds · 4
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Works count: 40
Citation count: 1,321
H-index: 17
I10-index: 21
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