Patent Number: 047754958
Section: claims

1. A process for disposing of a radioactive liquid waste, which comprises adding an alkaline earth metal hydroxide to a radioactive liquid waste containing sodium sulfate to convert said sodium sulfate into an insoluble alkaline earth metal salt thereof with the formation of sodium hydroxide as a by-product, adding a silicon oxide compound to the sodium hydroxide by-product to form water glass (sodium silicate), and solidifying said insoluble alkaline earth metal salt using said water glass. 2. A process for disposing of a radioactive liquid waste according to claim 1, wherein the radioactive liquid waste contains sodium sulfate as the main component. 3. A process for disposing of a radioactive liquid waste according to claim 2, wherein the alkaline earth metal hydroxide is barium hydroxide. 4. A process for disposing of a radioactive liquid waste, which comprises adding an alkaline earth metal hydroxide to a radioactive liquid waste containing sodium sulfate to form an insolubilized solid component and a remaining aqueous solution component containing sodium hydroxide, separating said insolubilized solid component from the aqueous solution component containing sodium hydroxide, adding a silicon oxide compound to the remaining aqueous solution of sodium hydroxide to form water glass, and solidifying said insolubilized solid component with a solidifier including said water glass. 5. A process for disposing of a radioactive liquid waste according to claim 4, wherein a mixture of the radioactive liquid waste and the alkaline earth metal hydroxide is kept at 40.degree. to 80.degree. C. and stirred to insolubilize the sodium sulfate. 6. A process for disposing of a radioactive liquid waste according to claim 5, wherein the mixture of the formed aqueous sodium hydroxide solution and the silicon oxide compound added thereto is stirred at a temperature of about 80.degree. C. to form water glass. 7. A process for disposing of a radioactive liquid waste according to claim 4, wherein the alkaline earth metal hydroxide is barium hydroxide. 8. A process for disposing of a radioactive liquid waste according to claim 4, wherein the radioactive liquid waste contains sodium sulfate as the main component. 9. A process for disposing of a radioactive liquid waste, which comprises the steps of adding an alkaline earth metal hydroxide to a radioactive liquid waste containing sodium sulfate to form a mixture of an insolubilized solid component and an aqueous sodium hydroxide solution; adding a silicon oxide compound to the liquid mixture while stirring the liquid mixture to form water glass mixed with the insolubilized solid compound; evaporating water contained in the liquid mixture comprising the insolubilized solid component and the water glass thus formed thereby to concentrate the liquid mixture; and adding a hardening agent to the concentrated liquid mixture to obtain a waste package. 10. A process for disposing of a radioactive liquid waste according to claim 9, wherein the radioactive liquid waste contains sodium sulfate as the main component. 11. A process for disposing of a radioactive liquid waste according to claim 10 wherein the alkaline earth metal hydroxide is barium hydroxide. 12. A process for disposing of a radioactive liquid waste according to claim 11, wherein the mixture of the radioactive liquid waste and the alkaline earth metal hydroxide is stirred at a temperature in the range of 40.degree. to 80.degree. C. to insolubilize the sodium sulfate. 13. A process for disposing of a radioactive liquid waste according to claim 12, wherein a silicon oxide compound is added to the formed aqueous sodium hydroxide solution and the mixture is stirred at a temperature kept at about 80.degree. C. to form water glass. 14. A process for disposing of a radioactive liquid waste according to claim 9, wherein the mixture comprising the formed water glass and the insolubilized solid component is dried and pulverized and then water and a hardening agent are added thereto to obtain the waste package. 15. A process for disposing of a radioactive liquid waste according to claim 9, wherein the ratio of silicon oxide (SiO.sub.2) to sodium oxide (Na.sub.2 O) in the water glass is in the range of 1 to 4. 16. A process for disposing of a radioactive liquid waste according to claim 15, wherein the ratio of silicon oxide to sodium oxide in the water glass is in the range of 2 to 3. 17. In a process for treating a radioactive liquid waste containing sodium sulfate for disposal comprising adding a silicon oxide compound to the radioactive liquid waste containing sodium sulfate to form water glass, and adding a hardening agent to said water glass to form a solidified body, the improvement which comprises: (1) adding an alkaline earth metal hydroxide to the radioactive liquid waste containing sodium sulfate to form an insoluble alkaline earth metal salt and an aqueous sodium hydroxide solution, (2) adding a silicon oxide compound to the resultant sodium hydroxide solution to form an insoluble alkaline earth metal salt-water glass mixture, and (3) adding a hardening agent to said mixture to form a solidified body. 18. A process for disposing of a radioactive liquid waste according to claim 17, wherein the mixture comprising the formed water glass and the insolubilized solid component is dried, pulverized and pelletized and then water and a hardening agent are added thereto to obtain the waste package. 19. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17 wherein the radioactive liquid waste contains sodium sulfate as the main compound. 20. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the alkaline earth metal hydroxide is barium hydroxide. 21. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the mixture of the radioactive liquid waste and the alkaline earth metal hydroxide is stirred at a temperature in the range of 40.degree. to 80.degree. C. to insolubilize the sodium sulfate. 22. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the mixture comprising the formed water glass and the insolubulized solid component is concentrated. 23. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the mixture comprising the formed water glass and the insolubulized solid compound is dried, pulverized, and rewetted. 24. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the ratio of silicon oxide (SiO.sub.2) to sodium oxide (Na.sub.2 O) in the water glass is in the range of 1 to 4. 25. A process for treating a radioactive liquid waste containing sodium sulfate for disposal according to claim 17, wherein the ratio of silicon oxide (SiO.sub.2) to sodium oxide (Na.sub.2 O) in the water glass is in the range of 2 to 3. 26. A process for disposing of radioactive liquid waste, which comprises the steps of: adding barium hydroxide to a radioactive liquid waste containing sodium sulfate as the main component and stirring the liquid waste and the barium hydroxide added thereto to form a mixture of an insolubilized solid component of barium sulfate and an aqueous sodium hydroxide solution;  adding a silicon oxide compound to the mixture while stirring the mixture to form water glass mixed with the insolubilized solid compound, whereby the mixture is free of the sodium hydroxide;  evaporating water contained in the mixture of the insolubilized solid component and the water glass thus formed thereby to concentrate the liquid mixture; and,  adding a hardening agent to the concentrated mixture while stirring the mixture and adding water to obtain a waste package.