Patent Number: 047939478
Section: claims

1. A method for treating a radioactive waste liquid principally composed of sodium sulfate, which comprises: adding a hydroxide of an alkaline earth metal to said radioactive waste and combining the hdyroxide with the radioactive waste liquid thereby producing an insoluble precipitate;  adding a used ion exchange resin to the radioactive waste liquid and combining the resin with the waste liquid to produce an insoluble precipitate;  adding silicic acid to the radioactive waste;  precipitating the formed precipitates;  thereafter concentrating the radioactive waste liquid containing therein the precipitates and silicic acid; and  adding a sodium silccate hardening agent to the concentrated radioactive waste, mixing and solidifying the mixture to form an insoluble solid waste package.  adding a first substance to the radioactive waste liquid and thereby combining the first substance with the anions to form an insoluble precipitate;  adding a solid second substance composed of a used ion exchange resin or used cellulose filter aid that adsorbs cations to the waste liquid and thereby adsorbing the cations and producing the solid second substance with the cations adsorbed thereon; and  separating the insoluble precipitate and the solid second substance with the adsorbed cations from the liquid portion of the waste liquid and purifying the liquid portion.  adding to said radioactive waste liquid a solid second substnace composed of a used ion exchange resin or used cellulose filter aid thereby adsorbing the cations in said waste liquid with the second substance and forming a second insoluble precipitate; and  solidifying the mixture of said first and second precipitates with a solidifying agent to form a solid waste package.  combining the first substance with the anions thereby forming an insoluble first precipitate;  adding to said waste liquid a second substance composed of used ion exchange resin and adsorbing sodium ions in the waste liquid on said ion exchange resin thereby forming an insoluble second precipitate; and  solidifying said first and second precipitates with a solidifying agent to form a solid waste package.  separating a sufficient amount of said water for leaving an amount necessary for effecting said solidifying with a hydraulic solidifying agent. 2. The method of claim 1, wherein said step of concentrating includes drying the precipitates and silicic acid; and said step of adding the sodium silicate hardening agent includes adding and mixing water to produce the mixture. 3. A method for treating a radioactive waste liquid principally composed of soluble inorganic salt dissociated into anions and cations, comprising: 4. The method of claim 3, wherein the used ion exchange resin is generated from nuclear power plants and further thereby forms an insoluble precipitate with the cations. 5. A method for producing a waste package of radioactive waste, which comprises: adding a first substance to a radioactive waste liquid, composed of soluble inorganic salt dissociated into anions and cations; combining the first substance with the anions in said radioactive waste liquid, thereby forming an insoluble first precipitate; 6. The method for producing a waste package of radioactive waste according to claim 5, including separating said first and second precipitates from the liquid of the waste liquid prior to said step of solidifying. 7. The method according to claim 5, wherein the radioactive waste liquid is an aqueous solution mainly composed of at least one of sulfuric acid, boric acid, nitric acid, sodium sulfate, sodium borate and sodium nitrate, or a mixture of two or more of them. 8. The method according to claim 5, wherein the first substance which is combined with anions in the radioactive waste liquid is a hydroxide or an oxide of an alkaline earth metal. 9. The method according to claim 5, wherein a hydraulic solidifying agent is used as a solidifying agent for solidifying the precipitate. 10. The method according to claim 9, wherein the hydraulic solidifying agent is cement. 11. The method according to claim 9, wherein the hydraulic solidifying agent is an alkali silicate. 12. The method according to claim 9, wherein the water used for the setting of the hydraulic solidifying agent is a liquid portion which remained after separating the precipitate from the radioactive waste liquid. 13. The method according to claim 5, wherein the liquid portion used for the setting of the hydraulic solidifying agent is one which has been reformed to an extent equal to ordinary water. 14. A method for producing a waste package of radioactive waste, which comprises: adding a first substance composed of a hydroxide of an alkaline earth metal to a radioactive waste liquid principally composed of soluble sodium sulfate dissociated into anions and cations; 15. The method according to claim 14, wherein said steps of combining and adsorbing thereby produce the step of reforming the remaining waste liquid into ordinary water; 16. The method according to claim 14, wherein the alkaline earth metal is barium hydroxide, and the insoluble first precipitate is barium sulfate. 17. The method according to claim 16, wherein said step of combining is conducted while maintaining the temperature of the waste liquid at about 80 degrees C. 18. The method according to claim 17, wherein the step of adsorbing produces sodium hydroxide and wherein the amount of ion exchange resin added is about 2.3 times by weight the amount of produced sodium hdyroxide. 19. The method according to claim 15, wherein the hydraulic solidifying agent is an alkali silicate and its hardening agent. 20. The method according to claim 14, wherein the concentration of the radioactive waste liquid principally composed of sodium sulfate is 20-25% by weight. 21. The method according to claim 15, wherein the pH of the waste liquid reformed into ordinary water is 6-8.