B.S. in Energy Engineering, Politecnico di Milano, 2016
M.S. in Nuclear Engineering, Politecnico di Milano, 2018
M.S. in Nuclear and Energy Engineering, Politecnico di Torino, 2019
Ph. D. in Nuclear Engineering, University of California Berkeley, 2023
Other Professional Employment
ANS 20.2 Member, 2020 - Present
ASME Task Group on Graphite Issues in MSRs, 2022 - Present
Licensed Professional Engineer (Italy), 2020
Advanced Reactor Designs
Molten Salt Chemistry
Nuclear Chemical Engineering
Selected Articles in Journals
L. Vergari, R.O. Scarlat, R.Hayes & M.Fratoni. The corrosion effects of neutron activation of 2LiF-BeF2 (FLiBe). Nuclear Materials and Energy, 34,101289 (2023) https://doi.org/10.1016/j.nme.2022.101289.
L. Vergari, J. Quincey, G. Meric, T. Merriman, M. Hackett & R.O. Scarlat. Self-lubrication of Nuclear Graphite in Argon at High Temperature. Tribology International, 107946 (2022) https://doi.org/10.1016/j.triboint.2022.107946.
L. Vergari, J. Quincey, G. Meric & R.O. Scarlat. Microstructural characterization data for nuclear graphite samples generated during tribology testing in argon. Data in Brief, 18796 (2022) https://doi.org/10.1016/j.dib.2022.108796.
L. Langford, N. Winner, A. Hwang, H. Williams, L. Vergari, R.O. Scarlat, M. Asta. Constant-potential molecular dynamics simulations of molten salt double layers for FLiBe and FLiNaK. Journal of Chemical Physics, 157, 094705 (2022) https://doi.org/10.1063/5.0097697 .
L. Vergari, M. Nelson, A. Droster, C. Contescu, N. Gallego & R.O. Scarlat. Infiltration of molten fluoride salts in graphite: phenomenology and engineering considerations for reactor operations and waste disposal. Journal of Nuclear Materials, 154058 (2022) https://doi.org/10.1016/j.jnucmat.2022.154058 .
L. Vergari & R.O. Scarlat. Kinetics and Transport of Hydrogen in Graphite at High Temperature and the Effects of Oxidation, Irradiation and Isotopics. Journal of Nuclear Materials, 153142. (2022) https://doi.org/10.1016/j.jnucmat.2021.153142.
L. Vergari & R.O. Scarlat. The impact of neutron irradiation, graphite oxidation and fluorination on tritium uptake into and desorption from graphite in molten salt environments. Fusion Engineering and Design, 168, 112627. (2021) https://doi.org/10.1016/j.fusengdes.2021.112627.
L. Vergari & R.O. Scarlat. Thermodynamics of hydrogen in graphite at high temperature and the effects of oxidation, irradiation and isotopics. Journal of Nuclear Materials, 152797. (2021) https://doi.org/10.1016/j.jnucmat.2021.152797.
L. Vergari & M. Fratoni. Spent fuel management strategies for fluoride-cooled pebble bed reactors. Nuclear Engineering and Design, 378, 111189. (2021) https://doi.org/10.1016/j.nucengdes.2021.111189.
L. Vergari, A. Cammi & S. Lorenzi. Reduced order modeling for coupled thermal-hydraulics and reactor physics problems. Progress in Nuclear Energy, 140, 103899. (2021) https://doi.org/10.1016/j.pnucene.2021.103899 .
L. Vergari, A. Cammi & S. Lorenzi. Reduced order modeling approach for parametrized thermal-hydraulics problems: inclusion of the energy equation in the POD-FV-ROM method. Progress in Nuclear Energy, 118, 103071. (2020) https://doi.org/10.1016/j.pnucene.2019.103071 .
Articles in Conference Proceedings
L. Vergari & R.O. Scarlat. Infiltration of Molten Fluoride Salts in Graphite: Effects on Reactor Operation and Waste Disposal. ANS Transactions, 127(1), 463-465, 2022.
L. Vergari & R.O. Scarlat. Graphite in fluoride salts reactors: tritium sequestration, tribology, and salt infiltration. ANS Transactions, 126(1), 381‑384, 2022.
L. Vergari & M. Fratoni. Storage and Transportation Strategy for Fluoride‑salt‑cooled High‑temperature Reactors Spent Fuel. ANS Transactions, 123(1), 193‑196, 2020.
L. Vergari & M. Fratoni. Packaging TRISO. ANS Radwaste Solutions, Spring 2021
Future Leaders Society Induction, American Association of Colleges and University
Graduate Scholarship, American Nuclear Society (2022)
James F. Schumar Scholarship, American Nuclear Society (2021)
Young Researcher Award, Asia-Pacific Symposium on Tritium (2020)
Berkeley Graduate Fellow, University of California, Berkeley
Recent Courses Taught
NPRE 498 NC3 (NPRE 498 NC4) - Nuclear Chemical Engineering