Brine Transport Experiments in Granular Salt

To gain confidence in the predictive capability of numerical models, experimental validation must be performed to ensure that parameters and processes are correctly simulated. The laboratory investigations presented herein aim to address knowledge gaps for heat-generating nuclear waste (HGNW) disposal in bedded salt that remain after examination of prior field and laboratory test data. Primarily, we are interested in better constraining the thermal, hydrological, and physicochemical behavior of brine, water vapor, and salt when moist salt is heated (Jordan et al., 2014; Stauffer et al., 2015). The target of this work is to use run-of-mine (RoM) salt; however during FY2015 progress was made using high purity, granular sodium chloride.