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​​Mission: Develop the technological foundations to enable MSRs for safe and economical operations while maintaining a high level of proliferation resistance.
​​1) ​​MSRs can provi​de a substantial portion of the energy needed for the US to achieve net zero carbon emissions by 2050 and
​​​2) ​There is a need for an abundant energy worldwide for the foreseeable future.

​​​​Salt Chemistry





​​Salt Chemistry

Determination of the Thermophysical and Thermochemical Properties of Molten Salts - Experimentally and Computationally
MSR Radioisotopes

Developing new 
technologies to 
radioisotopes of
 interest to the MSR community
​Technology Development and Demonstration - Radionuclide Release

Radionuclide Release Monitoring, Sensors & Instrumentation, Liquid Salt Test Loop
​Advanced Materials

Development of materials surveillance technology Graphite/Salt Interaction De-risk the transition from 316H to higher performance alloy 709

​Mod & Sim

Identify, prioritize, and resolve technical gaps related to mechanistic source term (MST)
modeling and
simulation tools


What are Molten Salt Reactors?

A molten salt reactor (MSR) is any nuclear reactor that employs liquid halide salt to perform a significant function in-core.  MSRs include a broad spectrum of design options including:

  • ​liquid- and solid-fueled variants,
  • chloride- and fl​uoride-based fuel salts,
  • thermal, fast, time variant, and spatially varying neutron spectra,
  • wide range of reactor power scales,
  • intensive, minimal, or inherent fuel processing,
  • multiple different primary system configurations, and compatibility with
  • nearly all fuel cycles.

The breadth of the MSR design space presents a substantial challenge to the completeness and broad applicability of any technology development planning activity.  Dozens of design concepts are currently in some state of development, nearly all have been introduced in the past decade, and it is not currently possible to reasonably evaluate which designs will eventually be successful.  Nevertheless, MSRs have common characteristics and many technology development issues are broadly applicable to most MSRs​


Federal Manager (Acting)​
Janelle Eddins
Office NE-52

​National Technical Director
Patricia Paviet
Office: 509-372-5983 Cell: 208-757-2048

November 5-7, 2024
ORNL Annual Molten Salt Reactor Workshop, Oak Ridge, TN

August 18-22, 2024
ACS Fall Meeting - Mol​ten Salt Symposium, Denver, CO

MSR Awards
  • Reduction, Mitigation, and Disposal Strategies for the Graphite Waste of High Temperature Reactors​
  • ​​​Bridging the gap between experiments and modeling to improve design of molten salt reactors
  • ​​Integrated Effects of Irradiation and Flibe Salt on Fuel Pebble and Structural Graphite Materials for Molten Salt Reactors
​​​​​​​​​FY 2022 CINR MSR AWARDS​
  • ​​A Molten Salt Community Framework for  Predictive Modeling of Critical Characteristics​
  • ​Understand​ing the Interfacial Structure of the Molten Chloride Salts by in-situ Electrocapillarity and Resonant Soft X-ray Scattering (RSoXS)​
  • Nuclear Material Accountancy During Disposal and Reprocessing of Molten Salt Reactor Fuel Salts
  • Optical Basicity Determin​ation of MoltenFluoride Salts and its Influence on Structural Material Corrosion
  • ​​​Los Alamos National Laboratory to lead study of molten-salt nuclear reactor materials
​​​​​​​MSR Annual Campaign Review
MSR ​​Cou​rse​

​Molten Salt Thermal Properties Database (MSTDB)
  • Oak Ridge National Laboratory -- MSTDB​
Molten Salt Thermal Properties Working Group​

Presentations on Molten Salt Chemistry

GIF Webinars