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- W2061305524 abstract "Mercury forms sparingly soluble phases with I under certain conditions. Therefore, Hg minerals have been suggested as potential additives to a clay-based buffer material in a nuclear fuel waste disposal vault for the selective removal of 129 I from solution. In oxidizing systems containing HgS, clay (bentonite or kaolinite), and either a synthetic groundwater solution (SGW) or deionized, distilled water, it was found that Hg lowers the concentration of I − in solution to ∼10 −6 mol/L. X-ray diffraction analysis indicated that Hg 2 I 2 (s) is formed in these systems and is the phase controlling the level of I − in solution. At levels of I − below ∼10 −6 mol/L, all the I − is consumed in the formation of HgI 2 0 (aq) and no solid HgI phase can form. Bentonite has only a minor effect on the Hg/I system, and kaolinite has little or no effect. Theoretical calculations of the Hg system indicate that, under oxidizing conditions and when the levels of Cl − or Br − are ∼1 and 0.01 mol/L, respectively (values typical for deep groundwaters in the Canadian Shield), Hg 2 I 2 (s) is not able to decrease the I − activity below ∼10 −5 mol/L, because of the greater stability of H9 2 Cl 2 (s) and Hg 2 Br 2 (s) phases (in the experimental study, Hg 2 I 2 (s) is able to lower the level of I − below 10 −5 mol/L because the Cl − concentration in the SGW was lower (0.18 moVL) and there was no Br in the system). Furthermore, Hg-I minerals are not stable under reducing to mildly oxidizing conditions. The maximum level of 129 I in a disposal vault in Canada is likely to be much less than 10 −3.5 mol/L. Therefore, Hg can not significantly decrease the level of 129 I in solution. The results of this study indicate that Hg minerals would not be effective additives to a buffer material in a disposal vault in the Canadian Shield for the removal of '2'I from solution." @default.
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- W2061305524 date "1986-01-01" @default.
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- W2061305524 title "The potential effectiveness of mercury minerals in decreasing the level of iodine-129 in a nuclear fuel waste disposal vault" @default.
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- W2061305524 doi "https://doi.org/10.1016/0191-815x(86)90053-7" @default.
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