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Tammy L. Trowbridge

Observed names: T. L. Trowbridge, T. Trowbridge, T.L. Trowbridge, Tammy M. Trowbridge, Tammy Trowbridge, Trowbridge, Tammy L; Wertsching, Alan K; Pinhero, Patrick J; Crandall, David L
Observed institutions: Los Alamos National Laboratory, Pacific Northwest National Laboratory, Idaho National Laboratory, Government of the United States of America, University of Florida, TerraPower (United States)
ORCID: 0000-0002-3852-901X
Observed ORCID: 0000-0002-3852-901X
OpenAlex ID: A5014875361
Scanning electron microscopy examination of a Fast Flux Test Facility irradiated U-10Zr fuel cross section clad with HT-9
2017 · Jason M. Harp, Douglas L. Porter, et al. · Journal of Nuclear Materials · 88
Development and Testing of an Advanced Neutron-Absorbing Gadolinium Alloy for Spent Nuclear Fuel Storage
2006 · Ronald E. Mizia, Tedd E. Lister, et al. · Nuclear Technology · 37
Effects of heat treatment on U–Mo fuel foils with a zirconium diffusion barrier
2015 · Jan-Fong Jue, Tammy L. Trowbridge, et al. · Journal of Nuclear Materials · 32
Studies of the Corrosion Properties of Ni-Cr-Mo-Gd Neutron-Absorbing Alloys
2005 · T.E. Lister, R.E. Mizia, et al. · CORROSION · 27
Post-transient examination of performance of uranium silicide fuel and silicon-carbide composite cladding under reactivity-initiated accident conditions
2022 · Jason Schulthess, David Kamerman, et al. · Journal of Nuclear Materials · 21
Localized attack of a two-phase metal, scanning electrochemical microscopy studies of NiCrMoGd alloys
2005 · T.E. Lister, P.J. Pinhero, et al. · Journal of Electroanalytical Chemistry · 18
Optimizing the Diffusion Welding Process for Alloy 800H: Thermodynamic, Diffusion Modeling, and Experimental Work
2011 · Ronald E. Mizia, Denis E. Clark, et al. · Metallurgical and Materials Transactions A · 17
Investigation of constituent redistribution in U-Pu-Zr fuels and its dependence on varying Zr content
2021 · Thaddeus Rahn, Luca Capriotti, et al. · Journal of Nuclear Materials · 16
Postirradiation characterization of palladium as an additive for fuel cladding chemical interaction mitigation in metallic fuel
2021 · Fidelma G. Di Lemma, Tammy M. Trowbridge, et al. · Journal of Nuclear Materials · 15
Dynamic surface anneal: activation without diffusion
2005 · D. Jennings, A. Mayur, et al. · International Conference on Advanced Thermal Processing of Semiconductors · 13
Best practices for preparing radioactive specimens for EBSD analysis
2018 · Tanvi Ajantiwalay, Tammy Trowbridge, et al. · Micron · 12
An investigation of the failure modes in U-10Mo monolithic fuel irradiated to high burnup
2022 · Charlyne Smith, Jan-Fong Jue, et al. · Journal of Nuclear Materials · 9
Mechanical and Thermophysical properties of low enriched uranium-10wt% molybdenum rolled foils
2022 · Jason Schulthess, Michael Heighes, et al. · Journal of Nuclear Materials · 9
Elevated temperature tensile tests on DU–10Mo rolled foils
2018 · Jason Schulthess, Randy Lloyd, et al. · Journal of Nuclear Materials · 9
Electrochemical Corrosion Testing of Neutron Absorber Materials
2007 · Tedd Lister, Ron Mizia, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 9
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Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils
2023 · F.G. Di Lemma, J.F. Jue, et al. · Nuclear Materials and Energy · 8
Characterization Report for the MP-1 Experiment Fabrication Campaign
2020 · Rajib Kalsar, Fidelma Di Lemma, et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 7
Possible impacts of Mo chemical banding and second phase impurities on the irradiation behavior of monolithic U-10Mo fuels
2023 · Charlyne A. Smith, Jan-Fong Jue, et al. · Journal of Nuclear Materials · 5
Localized Corrosion of a Neutron Absorbing Ni-Cr-Mo-Gd Alloy
2005 · R. E. Mizia, T. E. Lister, et al. · NACE CORROSION Conference · 5
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Experimental Investigations into the Corrosion of Alloy 625 Using NaCl-PuCl3 Molten Salt in a Natural Circulation Microloop
2024 · Toni Karlsson, USDOE Office of Nuclear Energy (NE), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 4
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Microstructurally validated stable and predictable swelling in low-enriched uranium monolithic U-10Mo fuel mini-plates
2025 · William A. Hanson, Daniele Salvato, et al. · Journal of Nuclear Materials · 3
Contributions to the mechanistic understanding of the microstructural evolution in irradiated U-Mo dispersion fuel
2023 · Daniele Salvato, Charlyne A. Smith, et al. · Journal of Nuclear Materials · 3
MP1 Intermediate Characterization Report Summary
2018 · Fidelma Di Lemma, USDOE National Nuclear Security Administration (NNSA), et al. · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 3
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Integrated fiducial sample mount and software for correlated microscopy
2014 · Timothy R. McJunkin, Tammy L. Trowbridge, et al. · Review of Scientific Instruments · 3
Effect of heat treatment on the microstructure of medium burn-up U-Mo monolithic fuel foils
2024 · F.G. Di Lemma, T.L. Trowbridge, et al. · Journal of Nuclear Materials · 2
Works count: 46
Citation count: 378
H-index: 11
I10-index: 11
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