Low melting high lithia glass compositions and methods

• US 6,624,103 B2
• Filed: 05/08/2001
• Issued: 09/23/2003
• Est. Priority Date: 05/02/1998
• Status: Expired due to Fees

• Current Assignee: Savannah River Nuclear Solutions LLS
• Original Assignee: Westinghouse Savannah River Company
• Inventors: Jantzen, Carol M., Marra, James C., Cicero-Herman, Connie A., Pickett, John B.
• Primary Examiner(s): Sample, David
• Application Number:
  US09/850,777
• Publication Number:
  US 20010029753A1
• Time in Patent Office: 868 Days
• Field of Search: 501/63, 501/70, 501/72, 588/11, 588/14, 588/15, 588/252, 588/901
• US Class Current: 501/72
• CPC Class Codes: C03C 1/002 Use of waste materials, e.g. slags
• CPC Class Codes: C03C 3/064 containing boron
• CPC Class Codes: C03C 3/087 containing calcium oxide, e.g. common sheet or container glass
• CPC Class Codes: C03C 3/091 containing aluminium
• CPC Class Codes: C03C 3/105 containing aluminium
• CPC Class Codes: Y10S 588/901 Compositions

Abstract

The invention relates to methods of vitrifying waste and for lowering the melting point of glass forming systems by including lithia formers in the glass forming composition in significant amounts, typically from about 0.16 wt % to about 11 wt %, based on the total glass forming oxides. The lithia is typically included as a replacement for alkali oxide glass formers that would normally be present in a particular glass forming system. Replacement can occur on a mole percent or weight percent basis, and typically results in a composition wherein lithia forms about 10 wt % to about 100 wt % of the alkali oxide glass formers present in the composition. The present invention also relates to the high lithia glass compositions formed by these methods. The invention is useful for stabilization of numerous types of waste materials, including aqueous waste uranium oxides The decrease in melting point achieved by the present invention desirably prevents volatilization of hazardous or radioactive species during vitrification.

Claims

1. An alkali oxide-lime-silica glass suitable for immobilizing radioactive, hazardous, or mixed waste, consisting essentially of:

(a) SiO₂ in an amount ranging from about 46 wt % to about 66 wt %;

(b) CaO in an amount ranging from about 5 wt % to about 28 wt %;

(c) Na₂O in an amount ranging from about 1.9 wt % to about 25 wt %;

(d) Li₂O in an amount ranging from about 3 wt % to about 11 wt %; and

(e) a uranium oxide selected from the group consisting of U₃O₈ in the range from about 0.5 wt % to about 12 wt % and UO₂ in an amount ranging from about 0.4 wt % to about 12 wt %.

2. The alkali oxide-lime-silica glass composition according to claim 1 including:

(f) Al₂O₃ in an amount ranging from about 2.5 wt % to about 18 wt %.

3. The alkali oxide-lime-silica glass composition according to claim 1, further including:

(f) Fe₂O₃ in an amount ranging from about 0.9 wt % to about 13 wt %.

4. The alkali oxide-lime-silica glass composition according to claim 1, further including:

(f) K₂O in an amount ranging from about 0 wt % to about 1.8 wt %; and

(g) P₂O₅ in an amount ranging from about 0 wt % to about 4.5 wt %.