Personal profile
Biography
Dr. Thomas (Tommy) Fuerst joined the Fusion Safety Program at Idaho National Laboratory in 2019 as a research scientist. His research focus is hydrogen isotope interaction with fusion and fission materials and technology for tritium management in advanced reactors. His expertise is in measurement of hydrogen transport properties, membranes and membrane reactors for hydrogen separation, thin film deposition, and material characterization using techniques such as scanning auger microprobe, x-ray photoelectron spectroscopy, electron microscopy, and x-ray diffraction. Dr. Fuerst is a member of the executive committee for the American Nuclear Society Fusion Energy Division. When not researching tritium, he can be found in the mountains rock climbing, running, and skiing with his wife Meriel.
Education/Academic qualification
PhD, Chemical Engineering, Colorado School of Mines
Bachelor, Chemical Engineering, University of Colorado Boulder
External positions
Outgoing Joint Appointment, Colorado School of Mines
Expertise related to UN Sustainable Development Goals
In 2015, UN member states agreed to 17 global Sustainable Development Goals (SDGs) to end poverty, protect the planet and ensure prosperity for all. This person’s work contributes towards the following SDG(s):
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SDG 7 Affordable and Clean Energy
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SDG 13 Climate Action
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Collaborations and top research areas from the last five years
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Computational Fluid Dynamics Analysis of Lead-Lithium Dispersion Behavior in a Gas-Liquid Contactor for Tritium Extraction
Bowers, A. G., Fuerst, T. F. & Sharma, S. L., Mar 17 2026, In: Fusion Science and Technology.Research output: Contribution to journal › Article › peer-review
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Elucidating hydrogen isotope transport mechanisms in proton-conducting ceramics with trapping effects using TMAP8
Yang, L., Simon, P.-C., Tang, W., Li, M., Zhao, Z., Ding, D. & Fuerst, T., Feb 18 2026, In: International Journal of Hydrogen Energy. 210, 153551.Research output: Contribution to journal › Article › peer-review
Open Access -
Implementation of tritium transport in a gas-liquid contactor CFD simulation of tritium extraction from lead-lithium in ANSYS fluent
Bowers, A. G., Sharma, S. L. & Fuerst, T. F., Jan 2026, In: Fusion Engineering and Design. 222, 115479.Research output: Contribution to journal › Article › peer-review
2 Scopus citations -
The impact of argon addition on hydrogen superpermeation through palladium alloy metal foil pumps during direct internal recycling
Hufnagel, C. L., Camacho, V., Fuerst, T. F., Rutkowski, A., Way, J. D. & Wolden, C. A., Jan 2026, In: Fusion Engineering and Design. 222, 115428.Research output: Contribution to journal › Article › peer-review
Open Access1 Scopus citations -
Computational Fluid Dynamics Analysis of the Molten Salt Tritium Transport Experiment Test Section
Bowers, A. G., Sharma, S. L. & Fuerst, T. F., Oct 23 2025, (E-pub ahead of print) In: Fusion Science and Technology. 82, 1-2, p. 431-448 18 p.Research output: Contribution to journal › Article › peer-review
Activities
- 1 Membership of network
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American Nuclear Society (ANS) (External organization)
Fuerst, T. (Chair)
1900 → …Activity: Membership › Membership of network