2017
DOI: 10.1016/j.jct.2016.08.029
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Leaching of actinides and other radionuclides from matrices of Chernobyl “lava” as analogues of vitrified HLW

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Cited by 18 publications
(15 citation statements)
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“…This is somewhat unusual behaviour for alkali-aluminosilicate glasses (where the release of alkali elements to solution from the corroding glass and subsequent complexation with alkali elements raises the pH to alkaline values), and points to the formation of pH-influencing secondary alteration phases, such as those that incorporate hydroxide ions (removal of which may lower pH), or those that complex with carbonate ions. Within the Chernobyl sarcophagus, the carbonate concentration was found to vary between 370-2900 mg L −1 , and uranyl carbonate mineral phases were observed to form, 1,16,18,24,25 which may effectively lower the pH. However, the present experiments contained significantly less carbonate (only that in equilibrium with CO 2 in the air), and such phases were neither observed, nor predicted by geochemical modelling.…”
Section: Discussioncontrasting
confidence: 72%
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“…This is somewhat unusual behaviour for alkali-aluminosilicate glasses (where the release of alkali elements to solution from the corroding glass and subsequent complexation with alkali elements raises the pH to alkaline values), and points to the formation of pH-influencing secondary alteration phases, such as those that incorporate hydroxide ions (removal of which may lower pH), or those that complex with carbonate ions. Within the Chernobyl sarcophagus, the carbonate concentration was found to vary between 370-2900 mg L −1 , and uranyl carbonate mineral phases were observed to form, 1,16,18,24,25 which may effectively lower the pH. However, the present experiments contained significantly less carbonate (only that in equilibrium with CO 2 in the air), and such phases were neither observed, nor predicted by geochemical modelling.…”
Section: Discussioncontrasting
confidence: 72%
“…Other studies of fission product (e.g., Pu, Am, Cs and Eu) leaching from real LFCM have shown no real difference in the corrosion rate between the two compositions. 18 These crudely obtained uranium release rates should be treated with caution and no extrapolations to longer durations should be made, however, it is clear that the values obtained are approximately one order of magnitude greater than those for uranium leached from spent nuclear fuel under oxidative conditions, 33 but are comparable with those for U 3 O 8 -doped borosilicate glass. 34 The normalised mass loss values of Na and Si from the simulant LFCM compositions are also of the same order of magnitude as borosilicate high-level nuclear waste glass compositions such as MW25 35 or the non-radioactive simplified surrogate of French high-level waste glass, the International Simple Glass.…”
Section: Discussionmentioning
confidence: 89%
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