Developing a framework for thermodynamic measurements of fluoride salt nuclear fuel
Date
2019-10-01
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Abstract
With a single liquid acting simultaneously as a primary coolant and a nuclear fuel, molten salt reactor development has been challenged with understanding the behavior of its complex fluoride solution under various conditions. Experimental thermodynamics can address part of this challenge by providing insights into the system’s behaviour, such as melting points, heat capacities, and solubilities. The current work develops an experimental framework for studying the experimental thermodynamics of fluoride nuclear salt materials. By establishing experimental capabilities and practises, experimental routines are qualified with the goal of providing background on the environment of error of future thermodynamic measurements using differential scanning calorimetry. Infrastructure, standard procedures, a custom crucible, and qualification of a routine for thermodynamic measurements have been developed. Study on particle size reduction, material interactions, and techniques for purification demonstrated a promising environment for thermodynamic measurements.
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Keywords
Thermodynamics, Molten salt reactor, Nuclear