METHOD OF ELIMINATING RADIOACTIVE WASTES AND PRODUCTS THAT ARE OBTAINED ACCORDING TO THIS METHOD
Patent
·
OSTI ID:4834207
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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