Simfuel dissolution studies in granitic groundwater

I. Casas, M.S. Caceci, J. Bruno, A. Sandino, Kaija Ollila

    Research output: Book/ReportReport


    The dissolution behavior of an unirradiated chemical analogue of spent nuclear fuel (SIMFUEL) has been studied in the presence of two different synthetic groundwater at 25 deg C and under both oxic and anoxic conditions. The release of U, Mo, Ba, Y and Sr was monitored during static (batch) leaching experiments of long duration (about 250 days). Preliminary results from continuous flow-through reactor experiments are also reported. The results obtained indicate the usefulness and limitations of SIMFUEL in the study of the kinetics and mechanism of dissolution of the minor components of spent nuclear fuel. Molybdenum, barium and strontium have shown a trend to congruent dissolution with the SIMFUEL matrix after a higher initial fractional release. Yttrium release has been found to be solubility controlled under the experimental conditions. A clear dependence on the partial pressure of O2 of the rates of dissolution of uranium has been observed.
    Original languageEnglish
    Number of pages33
    Publication statusPublished - 1991
    MoE publication typeD4 Published development or research report or study

    Publication series

    SeriesYJT Report


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