Patent Number: 041742931
Section: claims

1. A process for the disposal of aqueous solutions containing radioactive waste material comprising; (a) densifying dry particulate portland cement in a sealable leak-proof container to a bulk density ranging from about 1.3 to about 1.8 grams per cubic centimeter, said cement having a particle size ranging from about 120 mesh to about 400 mesh;  (b) dispersing without mechanical agitation from about 15 weight percent to about 30 weight percent of the aqueous solution based upon the weight of the densified cement in-situ within the densified cement;  (c) sealing said densified cement containing said aqueous solution off from the atmosphere until the said aqueous solution is hydrated with said cement;  (d) impregnating the hydrated cement with a mixture of monomer and a polymerization catalyst and polymerizing the monomer in-situ within the pregnant hydrated cement;  (e) storing said pregnant hydrated cement in a suitable storage area;  (f) maintaining the temperature of the materials utilized in the process at a temperature below 99.degree. C. throughout steps a thru e of the process. 2. The process of claim 1 wherein type III portland cement is used. 3. The process of claim 2 wherein the temperature of the materials utilized in the process are maintained at a temperature below 90.degree. C. throughout steps a through e of the process. 4. The process of claim 3 wherein said monomer is styrene. 5. The process of claim 4 wherein the polymerization catalyst is 2,2 Azobis-2-methylpropionitrile. 6. The process of claim 5 wherein a safety seal of solid polystyrene is formed on the surface of said pregnant hydrated cement. 7. The process of claim 6 wherein the leak-proof container is a 55 gallon drum having leak-proof plastic liner.