Claims
- 1. A one-step process for converting radioactive metal waste into a product suitable for storage, comprising providing a cyclone reactor having means for heating the side walls thereof and an exhaust gas outlet and a glass product outlet, establishing an inlet stream of aspirated radioactive metal waste, establishing an inlet stream of air and silica, mixing the two inlet streams in the cyclone reactor to produce a glass and an off gas, maintaining the side walls of the reactor at a temperature sufficient to permit the glass formed in the reactor to flow along the side walls to the liquid glass outlet, and continuously venting off gas through the exhaust gas outlet.
- 2. The process of claim 1, and further including introducing an oxide selected from the group consisting of B.sub.2 O.sub.3, Al.sub.2 O.sub.3, MgO, CaO into the cyclone reactor with the silica to form a leach resistant glass.
- 3. The process of claim 1, wherein the side walls of the reactor are maintained at a predetermined temperature by heating coils connected to a source of heat in heat transfer relationship with the side walls to form a protective coating of glass on the side walls when the reaction begins.
- 4. The process of claim 3, wherein said heating coils are positioned inside the side walls.
- 5. The process of claim 3, wherein the radioactive waste includes sodium metal and the glass includes Na.sub.2 Si.sub.2 O.sub.5 and the temperature of the reactor is maintained in excess of about 1000.degree. C.
- 6. The process of claim 5, wherein the glass formed has up to about 30% by weight of Na.sub.2 O, at least 10% by weight of a combination of one or more of B.sub.2 O.sub.3, Al.sub.2 O.sub.3, CaO and MgO, and the balance SiO.sub.2.
- 7. The process of claim 5, wherein the Na.sub.2 O is present in an amount of from about 20% by weight to about 30% by weight, and B.sub.2 O.sub.3 is present in an amount greater than the combination of Al.sub.2 O.sub.3, CaO and MgO.
- 8. The process of claim 5, wherein the radioactive waste includes NaK and the glass includes Na.sub.2 O and K.sub.2 O.
- 9. The process of claim 8, wherein the glass formed has up to about 30% by weight of a combination of Na.sub.2 O and K.sub.2 O, at least 10% by weight of a combination of one or more of Ba.sub.2 O.sub.3, Al.sub.2 O.sub.3, CaO and MgO, and the balance SiO.sub.2.
- 10. The process of claim 8, wherein the Na.sub.2 O and K.sub.2 O are present in a combined amount of from about 20% by weight to about 30% by weight and B.sub.2 O.sub.3 is present in an amount greater than the combination of Al.sub.2 O.sub.3, CaO and MgO.
- 11. The process of claim 5, wherein the process is continuous.
- 12. The process of claim 11, wherein the amount of silica introduced per unit of time is not less than about 2.5 times the amount of radioactive metal waste.
- 13. The process of claim 12, wherein the reaction occurs at substantially atmospheric pressure.
- 14. A one-step process for converting radioactive metal waste into a product suitable for storage, comprising providing a reactor vessel having means for heating the walls thereof and an exhaust gas outlet and a product glass outlet, introducing radioactive alkali metal waste aspirated by nitrogen into the reactor vessel, introducing air and silica into the reactor vessel wherein the silica is present in an amount of about 2.5 times the amount of radioactive metal in one step at a temperature in excess of 1000.degree. C. to form a glass, and removing the glass from the reactor vessel.
- 15. The one-step process of claim 14, wherein the glass contains additives selected from the group consisting of the oxides of boron, aluminum, calcium and magnesium.
- 16. The one-step process of claim 15, wherein the alkali metal is sodium, the additives are present in an amount of up to about 10% by weight and boron oxide is present in a greater amount than other additives.
- 17. The one-step process of claim 16, wherein the sodium is present in the glass formed in an amount of from about 20% by weight to about 30% by weight.
CONTRACTUAL ORIGIN OF THE INVENTION
The U.S. Government has its rights in this invention pursuant to Contract No. W-31-109-ENG-38 between the U.S. Department of Energy and Argonne National Laboratory.
US Referenced Citations (16)
Non-Patent Literature Citations (2)
Entry |
DOE/HP-29, ANL-87-39, Rajan et al., "Improved Treatment/-Disposal of Reactive Metals", Annual Report, 10/1987. |
ANL-78-87, McPheeters et al., "Disposal of Radioactive Sodium Waste", ANL, dated Sep. 1978. |