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Benton E. Garrison
Benton E. Garrison
Oak Ridge National Laboratory
Materials science
Alloy
Embrittlement
Composite material
Zirconium alloy
5
Papers
13
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Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation
2021
Journal of Nuclear Materials
Thak Sang Byun
Benton E. Garrison
Michael McAlister
Xiang Chen
Maxim N. Gussev
Timothy G. Lach
A. Le Coq
Kory D. Linton
Chase Joslin
J.K. Carver
F.A. List
Ryan R. Dehoff
Kurt A. Terrani
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Citations (3)
Correlations of the Steam Oxidation Rate Constant of BWR Alloy Zircaloy-2 at 800–1400 °C
2021
Oxidation of Metals
Yong Yan
Benton E. Garrison
Andrew T. Nelson
Dan Lutz
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Determining failure properties of as-received and hydrided unirradiated Zircaloy-4 from ring compression tests
2021
Engineering Failure Analysis
Benton E. Garrison
Yong Yan
Stephanie C. TerMaath
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Mechanical failure of fresh nuclear grade iron–chromium–aluminum (FeCrAl) cladding under simulated hot zero power reactivity initiated accident conditions
2020
Journal of Nuclear Materials
Nicholas R. Brown
Benton E. Garrison
Richard R. Lowden
M. Nedim Cinbiz
Kory D. Linton
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Citations (2)
High-temperature oxidation kinetics of sponge-based E110 cladding alloy
2017
Journal of Nuclear Materials
Yong Yan
Benton E. Garrison
Michael Howell
G. L. Bell
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Citations (8)
1