Process for the preparation of a borosilicate glass containing nuclear waste

• US 4,797,232 A
• Filed: 04/06/1987
• Issued: 01/10/1989
• Est. Priority Date: 04/08/1986
• Status: Expired due to Term

• Current Assignee: Société Générale Pour Les Techniques Nouvelles (Government of France)
• Original Assignee: Société Générale Pour Les Techniques Nouvelles (Government of France)
• Inventors: Aubert, Bruno
• Primary Examiner(s): Locker, Howard J.
• Application Number:
  US07/035,051
• Time in Patent Office: 645 Days
• Field of Search: 252/629, 252/632, 501/12, 501/152, 501/153, 501/154, 501/155, 106/74, 423/326, 423/328, 423/329
• US Class Current: 588/12
• CPC Class Codes: G21F 9/162 in an inorganic matrix, e.g. clays, zeolites
• CPC Class Codes: G21F 9/305 Glass or glass like matrix C03B5/005 takes precedence; compositional aspects C03C

Abstract

The invention relates to a process for the preparation of a borosilicate glass containing nuclear waste.

In this process, an inactive borosilicate matrix is prepared in an aqueous medium by mixing the following:

a silica-based gel precursor,

a concentrated aqueous solution of a boron compound, and

a concentrated aqeuous solution of the vitrification adjuvant,

in proportions corresponding to the composition of the final glass minus the waste, with stirring at a high rate of shear, at a temperature of between 20° C. and 80° C., preferably at 65°-70° C., at an acid pH, preferably a pH of between 2.5 and 3.5, so as to form a gelled solution, and the said matrix is heat-treated and the nuclear waste is added at any stage during the said treatment to form, by melting, the final borosilicate glass containing the said waste.

The process according to the invention is applied to the treatment of nuclear waste, especially to solutions of fission products.

Claims

1. A process for the preparation of a borosilicate glass containing nuclear waste, wherein The process comprises the steps of:

(A) mixing

1. an inactive borosilicate matrix prepared in an aqueous medium by mixing the following;

2. a silica-based gel precursor,

3. a concentrated aqueous solution of a boron compound, and

4. a concentrated aqueous solution of a vitrification adjuvant,

with stirring at a high rate of shear, at a temperature of between 20°

C. and 80°

C. and at an acid pH, so as to form a gel;

(B) drying the gel to provide a dried gel;

(C) calcining the dried gel to form a calcined material;

(D) melting the calcinated material to form a melted glass;

(E) solidifying the melted glass; and

(F) adding an aqueous solution of nuclear waste or a calcinate thereof to the gel during one of the steps (B), (C) and (D) to form the borosilicate glass immobilizing the nuclear waste.

2. the process as claimed in claim 1, wherein the mixture to prepare the inactive matrix is effected with a stirrer which rotates at more than about 500 rpm.

3. The process as claimed in claim 2, wherein the mixing is done at about 65°

C. to 70°

C.

4. The process as claimed in claim 1, wherein the gel precursor is a sol.

5. The process as claimed in claim 1, wherein the silicon-based gel precursor is an alkaline colloidal silica.

6. The process as claimed in claim 1, wherein the silicon-based gel precursor is an acid colloidal silica.

7. The process as claimed in claim 1, wherein the boron compound is ammonium tetraborate.

8. The process as claimed in claim 1, wherein the boron compound is boric acid.

9. The process as claimed in claim 1, wherein the inactive matrix is dried at between 100°

and 200°

C., and then calcined at between 300° and

450°

C. to provide a calcinate, wherein the said calcinate is dispersed in the aqueous solution of nuclear waste and mixed by stirring, and wherein the resultant mixture is dried, calcined and then melted to form the final glass.

10. The process as claimed in claim 1, wherein the inactive matrix is dried at between about 100°

-105°

C., wherein the said dried gel is brought into contact with the aqueous solution of waste, with stirring, and wherein the resultant mixture is dried, calcined and then melted to form the final glass.

11. The process as claimed in claim 9, wherein the dried or calcined matrix and the solution of waste are introduced separately into a calciner, and wherein the mixing, drying and calcination are effected in the said calciner.

12. The process as claimed in claim 1, wherein the solution of waste is dried or calcined and the dried waste or calcinate of the waste is introduced separately into a melting furnace to form the final glass.

13. A process for immobilizing nuclear waste in the form of a liquid aqueous solution as a waste material, the process comprising the steps of:

A. simultaneously mixing glass-forming materials in an aqueous system, the ingredients comprising;

1. a silica gel precursor for forming silica in the final glass, the precursor being an aqueous suspension of colloidal silica;

2. a boron compound in an aqueous solution for forming boron oxide in the final glass; and

15. A process as defined in claim 13 in which other constitutents of the final glass as a vitrification adjuvant are added in Step A, the adding being simultaneous with the glass forming materials, the other constituents comprising a solution of an aluminum compound that forms Al₂ O₃ in the final glass.

17. A process as defined in claim 13 in which Step A is performed at about 65°

to 70°

C.

19. A process as defined in claim 13 in which the drying Step B is about 100°

to 105°

C.

20. A process as defined in claim 13 in which Step C is conducted at about 300°

to 450°

C.

21. A process as defined in claim 13 in which the silica gel precursor is an alkaline colloidal silica that provides a gel to provide the gel solidified mixture of Step A.

22. A process as defined in claim 13 in which the aqueous solution of 1 and 2 in Step A are concentrated in which the solutions are at least about 75% of their saturation concentrations.

14. an aqueous solution of vitrification adjuvant, the mixing being done at an acid pH and a temperature of about 20°

to 80°

C. to provide a gel solidified material;

B. drying the resultant solidified material to provide a dried gel;

C. calcining the dried gel of Step B at a temperature of about 300°

to 500°

C.;

D. melting the calcined product of Step C to form a melted glass;

E. solidifying the melted glass to form a borosilicate glass that encapsulates a nuclear waste material; and

F. adding an aqueous solution of nuclear waste or a calcinate of the aqueous solution of the nuclear waste to the dried material of step B or the calcined product of step C or the melted product of step D to provide the immobilized waste product.

16. A process as defined in claim 14 in which the other constituents comprises solutions of glass-forming compounds that form Na₂ O, ZnO, CaO and ZrO₂ in the final glass.

18. A process as defined in claim 16 in which the aqueous system of Step A has a pH of about 2.5 to 3.5.