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Brian Wirth

Brian D. Wirth

TVA Department Head and UT-ORNL Governorโ€™s Chair Professor of Computational Nuclear Engineering

Biography

Brian Wirth is the TVA Department Chair and UTโ€“ORNL Governorโ€™s Chair Professor of Computational Nuclear Engineering in the Department of Nuclear Engineering at the University of Tennessee, Knoxville.ย ย Professor Wirthโ€™s research investigates the performance of nuclear fuels, structural materials and plasma facing components in nuclear fission and fusion environments, utilizing computational materials modeling complemented by experimental investigation. Brian received a BS in nuclear engineering from the Georgia Institute of Technology in 1992 and a PhD in mechanical engineering from the University of California, Santa Barbara in 1998. Prior to joining UT, he was on the nuclear engineering faculty at the University of California, Berkeley and was a scientist at Lawrence Livermore National Laboratory.

 


Research

Computational multiscale materials modeling of nuclear fuel and structural materials performance in extreme nuclear fission and fusion environments. Experimental materials characterization techniques to quantify vacancies and gas behavior in solids, including position annihilation spectroscopy, thermal diffusion and gas permeation in solids. Diagnostic measurements of impurity transport in boundary fusion plasmas and thermography measurements and analysis of heat flux deposition on plasma facing surfaces of fusion reactors.


Education

University of California, Santa Barbara, Santa Barbara, CA.

PhD in Mechanical Engineering, Degree awarded: 12/1998

Georgia Institute of Technology, Atlanta, GA.

BS in Nuclear Engineering with Highest Honors, Degree awarded: 6/1992


Professional Service

  • Member, UTK Mossman Lecture Series Selection Committee, April 2022 โ€“ current.
  • Chairman, DOE Fusion Energy Sciences Advisory Committee (FESAC) Facilities Construction Projects Subcommittee, January 2024 โ€“ May 2024.
  • Member, Idaho National Laboratory Nuclear Science & Engineering Directorate Strategic Advisory Committee, April 2023 โ€“ present.
  • Member, ANS Honors and Award Committee, June 2021 โ€“ June 2027.
  • Member, United States National Academy of Sciences, Engineering and Medicine Committee to define the Key Goals and Innovations Needed for a U.S. Fusion Pilot Plant, July 2020 โ€“ March 2021ย 
  • Member, United Kingdom Atomic Energy Agency, Fusion Technical Advisory Group (F-TAG) for the Spherical Tokamak for Energy Production (STEP) project, 2022 โ€“ present.
  • Member, United States National Academy of Sciences, Engineering and Medicine, Committee to define A Strategic Plan for U.S. Burning Plasma Research, June 2018 โ€“ February 2020.ย 

Awards and Recognitions

  • American Nuclear Society (ANS) Fellow
  • 2016 American Nuclear Society Mishima Award for outstanding work in nuclear fuels and materials research
  • 2014 Department of Energy, Ernest Orlando Lawrence Award in Energy Science and Innovation
  • ย  ย  2007 Fusion Power Associates David J. Rose Excellence in Fusion Engineering Awardย 
  • ย  2006 National Science Foundation CAREER Award
  • ย ย 2003 Presidential Early Career Award for Scientists and Engineers (PECASE)

Publications

A full list of Wirth's publications is available at his Google Scholar Profile.

 

  • J. Rizk, J.W. McMurray and B.D. Wirth, โ€œBoron and lithium aqueous thermochemistry to model CRUD deposition in pressurized water reactorsโ€,ย Journal of Chemical Thermodynamics 195ย (2024) 107289.
  • L. Yang and B.D. Wirth, โ€œFirst-principles study of diffusion of intrinsic defects in tungsten boridesโ€,ย Journal of Nuclear Materialsย 591(2024) 154931.
  • C.G. Ghezzi, B.D. Wirth and N.R. Brown, โ€œTRISO burnup-dependent failure analysis of a HTGR design basis accident using BISONโ€,ย Nuclear Science & Engineeringย 198ย (2024) 1036-1050.
  • D.G. Whyte, C. Paz-Soldan and B. Wirth, โ€œThe academic research ecosystem required to support the development of fusion energyโ€,ย Physics of Plasmasย 30(2023) 090604.
  • D. Dasgupta, S. Blondel, E. Martinez, D. Maroudas, and B.D. Wirth, โ€œImpact of Soret effect on hydrogen and helium retention in PFC tungsten under ELM-like conditionsโ€,ย Nuclear Fusionย 63(2023) 076029.
  • G. Singh and B.D. Wirth, โ€œImpact of circumferential variation in power, neutron flux and spacer grids on structural behavior of SiC-SiC claddingโ€,ย Journal of Nuclear Materialsย 565ย (2022) 153726.
  • L. Yang and B.D. Wirth, โ€œBoron segregation and effect on hydrogen energetics near tungsten surfaces: A first-principles studyโ€,ย Surface Scienceย 717(2022) 121983.
  • M.R. Gilbert, K. Arakawa, Z. Bergstrom, M.J. Caturla, F. Gao, A.M. Goyaneva, S.Y. Hu, X. Hu, R.J. Kurtz, A. Litnovsky, J. Marian, M.-C. Marinica, E. Martinez, E.A. Marquis, D.R. Mason, B.N. Nguyen, P. Olsson, Y. Osetskiy, D. Senor, W. Setyawan, M.P. Short, T. Suzudo, J.R. Trelewicz, T. Tsuru, G.S. Was, B.D. Wirth, L. Yang, Y. Zhang, and S.J. Zinkle, โ€œPerspectives on multiscale modeling and experiments to accelerate materials development for fusionโ€,ย Journal of Nuclear Materialsย 554(2021) 153113.ย 
  • S. Taller, G. VanCouvering, B.D. Wirth, and G.S. Was, โ€œPredicting Structural Material Degradation in Advanced Nuclear Reactors with Ion Irradiationโ€,ย Scientific Reportsย 11ย (2021) 2949.ย 
  • G.R. Odette, M.J. Alinger and B.D. Wirth, โ€œRecent Developments in Irradiation-ย ย ย ย ย ย ย ย  Resistant Steelsโ€, Annual Review of Materials Researchย 38ย (2008) 471-503/li>
Brian Wirth

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