Properties of radioactive wastes and waste containers. Progress report No. 7, October--December 1977

Technical Report · Sat Apr 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/6552774· OSTI ID:6552774

Colombo, P.

Trial solidifications were made using portland type II cement--sodium silicate as the solidification agent. The sodium silicate was found to produce an initial rapid set for all wastes because of the precipitation of relatively insoluble silicate compounds upon reaction with soluble multivalent cations in solution in the cement-waste mixture. Achievement of the ultimate waste form strength required time intervals similar to waste forms produced using portland cement alone. A hard waste form was not obtained within seventy-eight days with formulations used to solidify boric acid waste. The flash points and flame points of Pioneer 221 bitumen and bitumen waste forms were determined using the Cleveland open cup method. The bitumen alone had a flash point of 610 +- 2/sup 0/F and a flame point of 668 +- 4/sup 0/F. The bitumen waste forms exhibited similar flame points but slightly higher (15 to 20/sup 0/F) flash points were measured. Self-irradiation exposure dose curves were calculated for BWR and PWR waste forms. These curves indicate the cumulative waste form exposure dose with time and serve as the basis for radiation stability experiments. Waste form specific activities of 0.01 to 100 Ci/ft/sup 3/ were considered. Bitumen waste forms containing sodium sulfate from the solidification of BWR chemical regenerative waste were prepared and leach tested. These specimens swelled and cracked during leach testing, exposing substantial new surface area to the leachant. The volumetric efficiencies of urea-formaldehyde and portland type II cement for various wastes and waste/binder ratios were calculated from compression test specimen data.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6552774
• Report Number(s): BNL-NUREG--50837
• Country of Publication: United States
• Language: English

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALKALI METAL COMPOUNDS
BITUMENS
BORIC ACID
BUILDING MATERIALS
BWR TYPE REACTORS
CEMENTS
COMBUSTION PROPERTIES
CONTAINERS
DISSOLUTION
HYDROGEN COMPOUNDS
INORGANIC ACIDS
IRRADIATION
LEACHING
MANAGEMENT
MATERIALS
ORGANIC COMPOUNDS
OTHER ORGANIC COMPOUNDS
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PORTLAND CEMENT
PROCESSING
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
REACTORS
SELF-IRRADIATION
SEPARATION PROCESSES
SILICATES
SILICON COMPOUNDS
SODIUM COMPOUNDS
SODIUM SILICATES
SOLIDIFICATION
TAR
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS