METHOD FOR DISPOSING OF RADIOACTIVE WASTE AND RESULTANT PRODUCT
A disposal method for radioactive wastes that permits use of the resultant product for air heating and sterilization is described. Radioactive liquid wastes are absorbed by highly porous and absorptive ceramic materials composed of Georgia kaolin, bentonite, feldspar, talc, and whiting (the % composition depends on the waste composition); subsequent heating and glazing seal the ceramic forms that may be of various shapes for the uses mentioned above. (D.C.W.) energy installations. The water was treated by a scavenging- precipitation with sodium hydroxide, pH 11.7, and ferrous sulfate, copperas-5 ppm Fe, to remove suspended solids and soluble hardness, clarified, and then passed through a carboxylic-phenolic ion-exchange resin to sorb the remaining radionuclides. After passage of 1,500 to 2,000 resin-bed volumes, the resin was eluted with 10 volumes of 0.5 M HNO/sub 3/. Sodium carbonate can be added in the precipitation step to aid the quantitative precipitation of calcium for wastes that contain small amounts of phosphates, or alternatively, an extra ion-exchange column of carboxylic resin can be used to remove calcium and thus conserve the capacity of the phenolic resin for cesium and strontium. Three kinds of studies were made: batch laboratory-scale studies, continuous nonradioactive runs at 15 liters/hr, and runs with radioactive waste at 60 liters/hr. These studies led to a pilot-plant demonstration of the process. The process is similar to that reported in ORNL-3036, which describes the use of a sulfonic-phenolic resin and a 5 M HCl regenerant. (auth)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-17-028587
- Assignee:
- Coors Porcelain Co.
- Patent Number(s):
- US 3093593
- OSTI ID:
- 4702915
- Resource Relation:
- Patent File Date: 1958 Jul 14; Other Information: Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
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