Research output per year
Research output per year
Personal profile
Biography
Dr. Charles Folsom is a fuel performance analyst in the Fuel Development, Performance and Qualification group at Idaho National Laboratory. His current work is in the design and analysis of experiments for the Transient Reactor Test (TREAT) facility at INL. Dr. Folsom has a BS in Mechanical engineering from Brigham Young University–Idaho and a MS and PhD from Utah State University. His graduate research involved multiphysics modeling of nuclear fuel performance for Accident Tolerant Fuel (ATF) concepts under reactivity-initiated accidents. Dr. Folsom has authored 21 journal publications, 1 patent application, and more than 30 peer-reviewed publications.
Research Interests
Thermal hydraulics, heat transfer, experiment design, irradiation experiments, and nuclear fuel performance analysis.
Education/Academic qualification
PhD, Mechanical Engineering, Utah State University
Award Date: Jan 1 2016
Master, Mechanical Engineering, Utah State University
Award Date: Jan 1 2012
Bachelor, Mechanical Engineering, Brigham Young University - Idaho
Award Date: Jan 1 2010
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Collaborations and top research areas from the last five years
Recent external collaboration on country/territory level. Dive into details by clicking on the dots or
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Characterization of Fuel-to-Coolant Heat Transfer During Reactivity-Initiated Accidents Using Tightly Coupled Thermal Hydraulics and Fuel Thermomechanics
Fox, M. A., Gorton, J. P., Folsom, C. P. & Brown, N. R., Jun 13 2025, In: Nuclear Technology. p. 1-24 24 p.Research output: Contribution to journal › Article › peer-review
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Evaluation of Loss-of-Coolant Commissioning Experiments Performed at Idaho National Laboratory
Armstrong, R., Folsom, C., Duarte, J. P., Corradini, M. & Jensen, C., Oct 5 2025, TopFuel 2025: Nuclear Reactor Fuel Performance Conference.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Future Opportunities for LWR Irradiations in US Test Reactors
Woolstenhulme, N., Oldham, N., Fleming, A., Anderson, K., Folsom, C., Gorton, J. P., Linton, K., Carpenter, D. & Kohse, G., Oct 5 2025, TopFuel 2025: Nuclear Reactor Fuel Performance Conference.Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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A knowledge gap analysis for transient CHF prediction within RELAP5-3D
Meehan, N. A., Folsom, C. P. & Brown, N. R., Jun 2024, In: Nuclear Engineering and Design. 422, 113171.Research output: Contribution to journal › Article › peer-review
2 Scopus citations -
Dynamic system scaling/similarity analysis of accelerated irradiation testing of uranium dioxide fuel
Ferguson, I. T., Chen, T., Yoshiura, R. K., Folsom, C. P. & Wachs, D. M., Jun 2024, In: Transactions of the American Nuclear Society. 130, 1, p. 493-495 3 p.Research output: Contribution to journal › Conference article › peer-review
Prizes
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INL Laboratory Director Award, Outstanding Impact Award
Jensen, C. (Recipient), Anderson, K. (Recipient), Fleming, A. (Recipient), Folsom, C. (Recipient), Ramirez, M. (Recipient) & Pavey, T. (Recipient), 2023
Prize: Honorary award
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INL Laboratory Director Award, Outstanding Impact Award
Woolstenhulme, N. (Recipient), Jensen, C. (Recipient), Imholte, D. (Recipient), Folsom, C. (Recipient) & Race, C. (Recipient), 2020
Prize: Honorary award
Activities
- 2 Membership of network
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American Nuclear Society (ANS) (External organization)
Folsom, C. (Member)
2023 → …Activity: Membership › Membership of network
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American Society of Mechanical Engineers (ASME) (External organization)
Folsom, C. (Member)
2023 → …Activity: Membership › Membership of network