Michael T. Benson
Current Organizations / Institutes
The organizations/institutes from the scholar's latest article
Previous Organizations / Institutes
The organizations / institutes from the scholar's other articles in the past ten years
Michael T. Benson has a total of 190 co-authors. Here are the top co-authors by number of shared publications:
Robert D. Mariani
15 shared publications- Yi Xie
School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907, USA
13 shared publications - James A. King
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
7 shared publications Thomas R. Cundari
The University of Memphis
7 shared publicationsTiankai Yao
7 shared publicationsJames A. King
6 shared publications
Latest Publications
- Open Access
- 15 September 2026
- Published by IOP Publishing in Progress in Energy
- Vol. 8 (4) , 045001
Efficient synthesis of proton-conducting electrolyte with nano-sized particle precursors: enhanced performance and cost reduction for protonic ceramic electrochemical cells
Protonic ceramic electrochemical cells (PCECs) are promising platforms for efficient energy conversion, hydrogen production, and high-value chemical synthesis at intermediate temperatures. However, large-scale deployment of PCECs remains constrained by the poor sinterability, high fabrication cost, and long processing time associated with state-of-the-art proton-conducting ceramic (PCC) electrolytes. Here, we report a time-efficient, ball-milling-free solid-state reaction approach using nano-sized precursor particles (n-SSR) to synthesize Ba (Zr,Ce,Y,Yb)O 3− δ proton-conducting electrolytes with enhanced manufacturability and performance. Compared with the conventional solid-state reaction route using micro-sized precursors ( μ -SSR), the n-SSR process largely shortens powder fabrication time by eliminating ball-milling process while producing fine electrolyte particles (200–600 nm) with superior sintering activity. As a result, PCECs fabricated with n-SSR electrolytes exhibit lower densification temperature and markedly improved electrochemical performance, delivering a 32% higher peak power density in fuel cell mode and a 40% higher electrolysis current density at 600 °C, primarily due to reduced ohmic resistance. Long-term stability exceeding 500 h without measurable degradation is demonstrated. Importantly, a techno-economic analysis reveals that the n-SSR process reduces total electrolyte fabrication costs by 25%–29% by minimizing comminution, calcination time, and processing complexity. Large-area (5 cm × 5 cm) single-cell fabrication further validates the scalability of this approach. These results establish n-SSR as a practical and generalizable manufacturing strategy for high-performance PCCs, addressing a key bottleneck for the large-scale deployment of protonic ceramic energy technologies.
- 15 September 2026
- Published by IOP Publishing in Progress in Energy
- Vol. 8 (4) , 045001
Open AccessEfficient synthesis of proton-conducting electrolyte with nano-sized particle precursors: enhanced performance and cost reduction for protonic ceramic electrochemical cells
Protonic ceramic electrochemical cells (PCECs) are promising platforms for efficient energy conversion, hydrogen production, and high-value chemical synthesis at intermediate temperatures. However, large-scale deployment of PCECs remains constrained by the poor sinterability, high fabrication cost, and long processing time associated with state-of-the-art proton-conducting ceramic (PCC) electrolytes. Here, we report a time-efficient, ball-milling-free solid-state reaction approach using nano-sized precursor particles (n-SSR) to synthesize Ba (Zr,Ce,Y,Yb)O 3− δ proton-conducting electrolytes with enhanced manufacturability and performance. Compared with the conventional solid-state reaction route using micro-sized precursors ( μ -SSR), the n-SSR process largely shortens powder fabrication time by eliminating ball-milling process while producing fine electrolyte particles (200–600 nm) with superior sintering activity. As a result, PCECs fabricated with n-SSR electrolytes exhibit lower densification temperature and markedly improved electrochemical performance, delivering a 32% higher peak power density in fuel cell mode and a 40% higher electrolysis current density at 600 °C, primarily due to reduced ohmic resistance. Long-term stability exceeding 500 h without measurable degradation is demonstrated. Importantly, a techno-economic analysis reveals that the n-SSR process reduces total electrolyte fabrication costs by 25%–29% by minimizing comminution, calcination time, and processing complexity. Large-area (5 cm × 5 cm) single-cell fabrication further validates the scalability of this approach. These results establish n-SSR as a practical and generalizable manufacturing strategy for high-performance PCCs, addressing a key bottleneck for the large-scale deployment of protonic ceramic energy technologies.
- Open Access
- 17 June 2024
- Published by AIP Publishing in Journal of Applied Physics
- Vol. 135 (23)
Uniaxial compressive creep tests by spark plasma sintering of 70% theoretical density α-uranium and U-10Zr
Metallic fuels hold numerous advantages over conventional uranium dioxide fuels and are a key component of several liquid metal-cooled advanced reactor concepts including sodium fast reactors. These fuels undergo rapid swelling during early burnup; consequently, they spend most of their reactor lifetime in a porous state. The presence of this porosity alters many of the mechanical properties of the fuel including creep impacting fuel deformation during axial swelling. This work investigates the creep behavior of the porous fuel using a spark plasma sintering technique. Creep tests were performed for the first time on porous α-phase uranium and uranium with 10 wt. % zirconium (U-10Zr) samples. The samples of α-phase uranium and U-10Zr were fabricated from depleted uranium by spark plasma sintering and subjected to uniaxial compressive creep testing. Calculated stress exponents were found to be 2.6±1.6 and 5.7±1.4 for α-U and U-10Zr, respectively, and calculated activation energies were found to be 61.6±1.1kJ/mol for α-U. The creep data were also used to evaluate existing porosity inclusive in creep models.
- 17 June 2024
- Published by AIP Publishing in Journal of Applied Physics
- Vol. 135 (23)
Open AccessUniaxial compressive creep tests by spark plasma sintering of 70% theoretical density α-uranium and U-10Zr
Metallic fuels hold numerous advantages over conventional uranium dioxide fuels and are a key component of several liquid metal-cooled advanced reactor concepts including sodium fast reactors. These fuels undergo rapid swelling during early burnup; consequently, they spend most of their reactor lifetime in a porous state. The presence of this porosity alters many of the mechanical properties of the fuel including creep impacting fuel deformation during axial swelling. This work investigates the creep behavior of the porous fuel using a spark plasma sintering technique. Creep tests were performed for the first time on porous α-phase uranium and uranium with 10 wt. % zirconium (U-10Zr) samples. The samples of α-phase uranium and U-10Zr were fabricated from depleted uranium by spark plasma sintering and subjected to uniaxial compressive creep testing. Calculated stress exponents were found to be 2.6±1.6 and 5.7±1.4 for α-U and U-10Zr, respectively, and calculated activation energies were found to be 61.6±1.1kJ/mol for α-U. The creep data were also used to evaluate existing porosity inclusive in creep models.
- 20 February 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 593
Manufacturing porous U-10Zr metallic fuels with controllable microstructure by volume control spark plasma sintering
- 20 February 2024
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 593
Manufacturing porous U-10Zr metallic fuels with controllable microstructure by volume control spark plasma sintering
- 9 September 2023
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 587
Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln
- 9 September 2023
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 587
Microstructural characterization of U-20Pu-10Zr-4Sb and U-20Pu-10Zr-4Sb-4Ln
- 17 December 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 574
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties
- 17 December 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 574
Manufacturing porous U10Zr fuels with controlled porosities by SPS and thermal properties
- 2 December 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 574
Grain growth kinetics of the gamma phase metallic uranium
- 2 December 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 574
Grain growth kinetics of the gamma phase metallic uranium
- 9 August 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 570
Transmission electron microscopy study of a high burnup U-10Zr metallic fuel
- 9 August 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 570
Transmission electron microscopy study of a high burnup U-10Zr metallic fuel
- 8 June 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 568, 153846
Transmission Electron Microscopy based Characterization of a U-20Pu-10Zr Fuel Irradiated in Experimental Breeder Reactor-II
- 8 June 2022
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 568, 153846
Transmission Electron Microscopy based Characterization of a U-20Pu-10Zr Fuel Irradiated in Experimental Breeder Reactor-II
- 1 May 2021
- Published by Elsevier in Materialia
- Vol. 16
Understanding spinodal and binodal phase transformations in U-50Zr
- 1 May 2021
- Published by Elsevier in Materialia
- Vol. 16
Understanding spinodal and binodal phase transformations in U-50Zr
- 1 February 2021
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 544
Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel
- 1 February 2021
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 544
Out-of-pile and postirradiated examination of lanthanide and lanthanide-palladium interactions for metallic fuel