TY - GEN
T1 - Roadmap for thermal property measurements of Molten Salt Reactor systems
AU - Mcmurray, Jake W.
AU - Johnson, Kaitlin
AU - Agca, Can
AU - Betzler, Benjamin R.
AU - Kropaczek, Dave J.
AU - Besmann, Theodore M.
AU - Andersson, David
AU - Ezell, N. Dianne Bull
PY - 2021
Y1 - 2021
N2 - Thermal properties of molten salts, both with and without fissile and fertile material, are fundamental to modeling and simulation that supports design, construction, operation, and accident progression evaluation of molten salt reactors. This roadmap provides guidance to the research community on the types and amounts of required data for base, or carrier, salt systems, recommends simulated burnup fuel salt compositions to evaluate, and provides a technical foundation for a focused salt property evaluation matrix. The property values generated from both computation and experimental methods are used to develop models that constitute the Molten Salt Thermal Properties Database (MSTDB). While the building blocks of MSTDB are fundamental in nature, its data facilitates constructing engineering models that allow stakeholders to investigate the behavior of specific compositions of interest and supports broader modeling and simulation of MSRs through coupling to multi-physics, multi-scale mass accountancy tools.
AB - Thermal properties of molten salts, both with and without fissile and fertile material, are fundamental to modeling and simulation that supports design, construction, operation, and accident progression evaluation of molten salt reactors. This roadmap provides guidance to the research community on the types and amounts of required data for base, or carrier, salt systems, recommends simulated burnup fuel salt compositions to evaluate, and provides a technical foundation for a focused salt property evaluation matrix. The property values generated from both computation and experimental methods are used to develop models that constitute the Molten Salt Thermal Properties Database (MSTDB). While the building blocks of MSTDB are fundamental in nature, its data facilitates constructing engineering models that allow stakeholders to investigate the behavior of specific compositions of interest and supports broader modeling and simulation of MSRs through coupling to multi-physics, multi-scale mass accountancy tools.
KW - 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
U2 - 10.2172/1778081
DO - 10.2172/1778081
M3 - Technical Report
CY - United States
ER -