New Measurements Enhance Molten Salt Reactor Development at Oak Ridge National Laboratory

Researchers at Oak Ridge National Laboratory have developed new methods to measure the thermal conductivity and viscosity of uranium-bearing molten salts, essential for molten salt reactor (MSR) modeling. Tools such as a variable gap system and rolling ball viscometer were utilized to evaluate candidate salt mixtures, generating unique data critical for MSR development.

This initiative is part of a broader collaboration among national laboratories to enhance the Molten Salt Thermal Properties Database, under the support of the Department of Energy's Office of Nuclear Energy. The findings could significantly impact the licensing and optimization processes for advanced nuclear technologies, as they address a gap in experimental data.