Patent Number: 041682432
Section: claims

1. The method of solidifying radioactive waste material for transport and long term storage, comprising: A. providing a mixture of radioactive waste material and water with said water being in an amount sufficient to meet a desired low hazard radiation classification when said mixture is solidified with urea-formaldehyde;  B. blending said mixture with a syrup, comprising an aqueous suspension of urea-formaldehyde in a partially polymerized state in an amount sufficient to solidify substantially all of the water present;  C. adding an acidic curing agent capable of promoting polymerization of said urea-formaldehyde in an amount sufficient to solidify said urea-formaldehyde in said mixture;  D. placing the resulting mixture in a storage container substantially as said curing agent is added; and  E. allowing said resulting mixture to gel and set in said container whereby a solid mass of the resin is obtained with the water and the radioactive components of said resulting mixture distributed therein.  A. transporting a liquid containing a setting agent in the form of a syrup comprising an aqueous suspension of urea-formaldehyde in a partially polymerized state to a reactor site in a supply tank;  B. pumping said setting agent at a controlled rate of flow from said tank to a blending chamber;  C. pumping waste liquids, containing water and radioactive material from the reactor, to said blending chamber at a controlled rate of flow proportioned to the rate of flow of said setting agent to provide a desired quantity ratio having an amount of urea-formaldehyde sufficient to solidify substantially all of the water present;  D. blending said waste liquids with said syrup in said blending chamber;  E. delivering the blended liquid mixture from said blending chamber to a receiving tank similar to said supply tank;  F. pumping an acidic liquid curing agent capable of promoting polymerization of said urea-formaldehyde in an amount sufficient to solidify said urea-formaldehyde in said mixture to interact with said liquid mixture within said receiving tank so as to cause said liquid mixture to solidify to a desired hardness;  G. allowing said resulting mixture to gel and set in said container whereby a solid mass of the resin is obtained with the water and the radioactive components of said resulting mixture distributed therein;  H. shielding the filled receiving tank against unwanted radioactive emission; and  I. transporting the shielded receiving tank to a disposal site.  A. intermixing such waste liquid with a liquid containing a setting agent in the form of a syrup comprising an aqueous suspension of urea-formaldehyde in a partially polymerized state capable of solidifying said waste liquid into a free standing hardened mass upon mixing with a curing agent;  B. adding an acidic curing agent capable of promoting polymerization of said urea-formaldehyde in an amount sufficient to solidify substantially all of the water present in said mixture;  C. placing the liquid mixture in a storage container substantially as said curing agent is added;  D. positioning non-liquid radioactive material having a higher level of radioactivity than said liquid mixture in the central area of said container prior to and during solidification of said liquid mixture; and  E. allowing said liquid mixture to gel and set in said container in surrounding relation to said material having a higher level of radioactivity whereby a solid mass of the resin is obtained with the water and the radioactive components of said liquid mixture distributed therein. 2. The method of claim 1 and in which said curing agent is intermixed with said blended syrup and radioactive waste material and water as they enter said container, and the resulting mixture in said container is agitated until it gels so as to distribute the radioactive waste evenly through said solid mass. 3. The method of claim 2 and wherein said container and the solid mass of urea-formaldehyde and radioactive waste material and water contained therein are buried in the earth for disposal. 4. The method of claim 3 and in which said container is shielded to prevent unwanted radioactive emissions to the surrounding environment during filling of said container, and said shielded container is thereafter transported to the burial site. 5. The method of claim 1 and wherein said radioactive waste material initially comprises a slurry of particulate solids in water, and a portion of said water is removed to provide said mixture of radioactive waste material in an amount sufficient to meet a desired low hazard radiation classification when solidified with urea-formaldehyde. 6. The method of claim 1 and wherein said radioactive waste material initially comprises a slurry of radioactive particulate solids in water, said particulate solids are dewatered to a damp state, and water thereafter is added to the dewatered particulate solids to provide said mixture of radioactive waste material in an amount sufficient to meet a desired low hazard radiation classification when solidified with urea-formaldehyde. 7. The method of claim 6 and wherein said radioactive particulate solids comprise spent ion exchange resin beads from the cooling system of a nuclear reactor. 8. The method of claim 6 and wherein said dewatering takes place in said container. 9. The method of claim 6 and wherein dewatered radioactive particulate solids are added to said container before said resulting mixture. 10. The method of claim 9 and wherein said dewatered radioactive particulate solids are confined centrally of said container so as to be surrounded and encapsulated by said resulting mixture as it gels and sets. 11. The method of claim 10 and wherein said radioactive particulate solids comprise spent ion exchange resin beads from the cooling system of a nuclear reactor. 12. The method of claim 10 and wherein said dewatered radioactive particulate solids confined centrally of said container have an average specific level of radioactivity higher than the surrounding solid mass whereby said solid mass provides a radiation shielding effect. 13. The method of claim 1 and wherein additional non-radioactive filler material is added to said mixture prior to introduction thereof into said container so as to reduce the low hazard radiation classification of said solid mass. 14. The method of claim 1 and wherein the proportion of said urea-formaldehyde to said curing agent is controlled to provide a desired curing time and hardening of said solid mass. 15. The method of claim 14 and wherein the curing time and hardening of said solid mass is further controlled by adding an inhibiting agent to said mixture, said inhibiting agent comprising ethylenediamine tetraacetic acid, disodium. 16. The method of claim 14 and wherein the curing time and hardening of said solid mass is further controlled by heating said mixture to speed up further polymerization. 17. The method of claim 1 and wherein additional amounts of said syrup and water and curing agent are mixed together and added to said container after said resulting mixture has been allowed to gel and set so as to fill up unoccupied areas of said container and take up any free water present therein. 18. The method of solidifying radioactive waste material for transport and long term storage, comprising: 19. The method of claim 18 and wherein said pumping of said waste liquids and said syrup and curing agent is accomplished by individual positive displacement pumps whereby the rate of flow of each is determined by the speed at which each corresponding pump is driven, and said pumps are driven at individually variable speeds for controlling the relative proportions of said waste liquids and said setting and curing agents being delivered to said receiving tank. 20. The method of claim 19 and wherein said individual pumps block flow of the material they pump when not being driven so as to prevent cross-contamination and unwanted solidification of said liquid mixture prior to entry into said receiving tank. 21. The method of claim 18 and wherein a water slurry of radioactive spent ion exchange resin beads is first pumped into said receiving tank, said resin beads are dewatered by removing the water component of said water slurry, and said liquid mixture and curing agent is then pumped into said receiving tank to surround and encapsulate said dewatered resin beads. 22. The method of claim 21 and wherein said liquid mixture and curing agent and dewatered resin beads are stirred together in said receiving tank as said liquid mixture solidifies. 23. The method of claim 18 and wherein additional radioactive solid materials are supported centrally of said receiving tank as said liquid mixture solidifies. 24. The method of claim 18 and wherein said radioactive solid materials include filter components. 25. The method of claim 18 and wherein a limited quantity of flush water is pumped through the system as filling of said receiving tank is completed to prevent unwanted solidification of said setting agent in the system. 26. A method for disposing of waste liquid containing water and radioactive material, comprising: 27. The method of claim 26 and wherein said materials having a higher level of radioactivity are retained within an enclosure mounted centrally of said container during filling of the container and gelling and setting of said liquid mixture. 28. The method of claim 27 and wherein said holding enclosure comprises a perforated basket, and said radioactive materials comprise a slurry of water and of particulate solids incapable of passing through the perforations in said basket whereby the liquid phase of said slurry falls from said basket through said perforations leaving said particulate solids in said basket, and said liquid phase is pumped from said container before said resulting mixture of blended syrup and radiation material and curing agent are placed in said container. 29. The method of claim 26 and wherein the proportions of said urea-formaldehyde and curing agent are controlled to delay gelling and setting of said liquid mixture until after said liquid mixture has surrounded said non-liquid radioactive materials positioned in the central area of said container. 30. The method of claim 26 and wherein additional non-radioactive filler material is mixed with said liquid mixture to dilute the hardened solid mass to desired Lowest Activity counts and provide additional shielding for said non-liquid radioactive material positioned in the central area of said container.