METHOD OF ELIMINATING RADIOACTIVE WASTES AND PRODUCTS THAT ARE OBTAINED ACCORDING TO THIS METHOD
Moist radioactive sludges are solidified by mixing 100 parts with 110 to 140 parts Portland cement and 1 to 3 parts sodium silicate. The solidified mass is coated with a polymerized resin, bitumen, or sodium silicate to increase the retention of the radioactive substances. (NPO) m impregnated charcoal for trapping or removing radioactive iodine, strontium, and tellurium at temperatures up to 900 deg F from the fuel element purge gas system of the HighTemperature Gas- Cooled Reactor is evaluated. The experimental apparatus used for duplicating the operating conditions anticipated in the reactor is described and a schematic diagram of the system is presented. The method in which the trapping reagent (aqueous silver acetate or ammoniacal silver acetate) is prepared is described. (N.W.R.)
- Research Organization:
- Originating Research Org. not identified
- NSA Number:
- NSA-15-033064
- OSTI ID:
- 4834207
- Report Number(s):
- FR 1246848
- Country of Publication:
- France
- Language:
- English
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