Abstract
The experimental solubility of transition metals in liquid alkali metal was compared to the modeled solubility calculated using various equations for solubility. These equations were modeled using the enthalpy calculations of the semi-empirical Miedema model and various entropy calculations. The accuracy of the predicted solubility compared to the experimental data is more dependent on which liquid alkali metal is being examined rather than the transition metal solute examined. For liquid lithium the calculated solubility by the model was generally larger than experimental values, while for liquid cesium the modeling solubility was significantly smaller than the experimental values. For liquid sodium, potassium, and rubidium the experimental solubilities were within the range calculated by this study. Few data approached the predicted temperature dependence of solubility and instead most data exhibited a less pronounced temperature dependence.
Highlights
Liquid alkali metals such as liquid sodium have been previously proposed as primary coolant in advanced nuclear reactors, with one of the Generation IV designs being a sodium-cooled fast reactor
Results parameter of 3000 K to calculate the entropy for the solubility of transition metals in liquid lithium
This stronger when considering the solubility of iron in the various liquid alkali the metals
Summary
Liquid alkali metals such as liquid sodium have been previously proposed as primary coolant in advanced nuclear reactors, with one of the Generation IV designs being a sodium-cooled fast reactor. Alkali metals are advantageous as coolants for they are liquids in the intermediate temperature range of nuclear reactors and provide excellent heat transfer properties as a coolant. For this reason the majority of the alkali metals have been considered in the past as coolants and have been extensively studied [1]. An integral part of this transport is the solubility limit of the transition metals and fission products in the liquid metal This solubility is of interest for coolant radioactivity and material degradation, such as fuel-cladding chemical interaction [3]. These calculations were compared to experimental data to show the accuracy of these various models
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