2012
DOI: 10.2172/1039996
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Summary of Fy11 Sulfate Retention Studies for Defense Waste Processing Facility Glass

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Cited by 4 publications
(8 citation statements)
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“…True sulfate saturation was achieved in [23] when the glass and salt were ground and melted 3 times, and gave the best known representation of true sulfate solubility in radioactive waste-type glasses. On the basis of [23] it is reasonable to expect that the sulfate solubility limit of the melts considered here was at least approached and is consistent with previously reported data (e.g., [9][10][11][12][13][14][15] …”
Section: Accepted Manuscriptsupporting
confidence: 90%
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“…True sulfate saturation was achieved in [23] when the glass and salt were ground and melted 3 times, and gave the best known representation of true sulfate solubility in radioactive waste-type glasses. On the basis of [23] it is reasonable to expect that the sulfate solubility limit of the melts considered here was at least approached and is consistent with previously reported data (e.g., [9][10][11][12][13][14][15] …”
Section: Accepted Manuscriptsupporting
confidence: 90%
“…A total of eleven experimental glasses were prepared in two inter-related series, Series A and B, which are broadly representative of U.S. high-level radioactive waste glasses (see, for example, [9,[11][12][13][14][15]). Analysed compositions of all glasses are shown in …”
Section: Methodsmentioning
confidence: 99%
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