Lead-iron phosphate glass as a containment medium for the...

G - Physics – 21 – F

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261/23, 359/37

G21F 9/00 (2006.01) C03C 3/16 (2006.01) G21F 9/30 (2006.01)

Patent

CA 1233839

LEAD-IRON PHOSPHATE GLASS AS A CONTAINMENT MEDIUM FOR THE DISPOSAL OF HIGH-LEVEL NUCLEAR WASTES ABSTRACT OF THE DISLOSURE Lead-iron phosphate glasses containing a high level or Fe2O3 for use as a storage medium for high-level radioactive nuclear waste. By combining lead-iron phosphate glass with various types of simulated high-level nuclear waste, a highly corrosion resistant, homogeneous, easily proceased glass can be formed. For corroding solution at 90°C., with solution pH values in the range between 5 and 9, the corrosion rate or the lead-iron phosphate nuclear waste glass is at least 102 to 103 times lower than the corrosion rate or a comparable borosilicate nuclear waste glass. The presence or Fe2O3 in forming the lead-iron phosphate glass is critical. Lead-iron phosphate nuclear waste glass can be prepared at temperatures as low as 800°C., since they exhibit very low melt viscosities in the 800 to 1050°C. temperature range. These waste-loaded glasses do not readily devitrify at temperatures as high as 550°C. and are not adversely affected by large doses of gamma radiation in H2O at 135°C. The lead-iron phosphate waste glasses can be prepared with minimal modification or the technology developed for processing borosilicate glass nuclear wasteforms.

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