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The SALT Research Group

UC Berkeley Nuclear Engineering Department

  • | Group
    • Raluca O. Scarlat
    • Haley Williams
    • Ryan Hayes
    • Alexandra (Sasha) Kennedy
    • Michael Borrello
    • D. Nathanael Gardner
    • Nicole Johnson
    • Sarah Heagy
    • Tim Pickarski
  • | Publications
  • | Projects
    • ThorCon Corrosion Project
    • NEUP – High Temperature Molten Salt Reactor Pump Development
    • NEUP – IRP Molten Salt Reactor Test Bed with Neutron Irradiation
    • Speciation of Light Elements in Molten Salts
    • FUTURE EFRC
    • Graphite and Tritium Studies in Molten Fluoride Salts
  • I INGSM-24 Conference
  • | Beryllium Safety
  • | Courses
  • | News & Events
    • Haley Williams Nominated to Give Presentation at the NEA Global Forum on Nuclear Education, Science, Technology and Policy
    • | Open House Nov. 2nd
    • | MS Round Robin 1.0
    • | Chemical Sensors Workshop 2020
    • | Molten Salt Bootcamp 2019
  • ThorCon Corrosion Project
  • NEUP – High Temperature Molten Salt Reactor Pump Development
  • NEUP – IRP Molten Salt Reactor Test Bed with Neutron Irradiation
  • Speciation of Light Elements in Molten Salts
  • FUTURE EFRC
  • Graphite and Tritium Studies in Molten Fluoride Salts

Graphite and Tritium Studies in Molten Fluoride Salts

The scope of this project is to study the interactions among graphite, fluoride salts and hydrogen isotopes in fluoride-cooled high-temperature reactors (FHRs). Some of the objectives of this project are:

  1. Measuring the contact angle between molten salt and graphite for variable chemistry of the salts and graphite history (virgin, irradiated, fluorinated, with and without friction).
  2. Studying the surface modification occurring to graphite when it is exposed to molten salts (with and without friction).
  3. Quantifying the impact of the presence of the salt in tritium uptake and desorption
  4. Developing an electrochemical technique for temperature-controlled hydrogen desorption, thus facilitating measurements on irradiated graphite samples
  5. Evaluating differences in the uptake and desorption mechanisms for irradiated graphite, irradiated + salt-exposed graphite and virgin graphite.

 

SALT Group Researchers

L. Vergari

Capabilities

  • Material preparation tools (Argon glovebox train for FLiBe work includes cutter, polisher, electrochemical cell, gas sparger, GCMS)
  • Material characterization techniques: SEM/EDS, XPS, XRD, Raman (including high-temperature Raman), Optical Microscopy (in FLiBe glove-box train)
  • High temperature cell for electrochemical techniques for gas uptake,  temperature-controlled desorption
  • Sessile drop setup for contact angle measurement
  • Data analysis and visualization (sci-kit learn, keras, OriginPro, CarbonX, SDP)
  • Thermodynamic modeling (HSC, FactSage)

Talks and Presentations

G. Meric, L. Vergari, J. Quincey, R. Scarlat, T. Merriman, M. Hackett, “Wear and Friction Behavior of Fuel Pebbles in Molten Fluoride Salt”, MiNES conference, November 10th, 2021, Pittsburgh (PA).

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Projects

  • FUTURE EFRC
  • ThorCon Corrosion Project
  • Molten Salt Reactor Test Bed with Neutron Irradiation
  • Graphite and Tritium Studies in Molten Fluoride Salts
  • NEUP – High Temperature Molten Salt Reactor Pump Development
  • NEUP – Probing Speciation of Light Elements in Molten Salts by Electrochemistry, High Temperature Liquid NMR, and Neutron Diffraction
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