Properties of radioactive wastes and waste containers. Quarterly progress report, October-December 1980
Simulated boric acid waste at three different concentrations was solidified in Portland III cement together with /sup 137/Cs, /sup 85/Sr, and /sup 60/Co. The leachability of these tracers from the waste forms was measured over a period of 84 days. Compressive strengths of the simulated waste forms at the three boric acid concentrations were also measured. An experiment was performed to determine the leachability of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from organic ion exchange resin/cement composites. Portland II and Lumnite cements were used as binders with waste-to-cement ratios of 1.0 and 1.8 by weight for both cements. In addition, the displacement of the three radiotracers from the ion exchange resins upon mixing the loaded resins with the two cements (before solidification) was measured. Cationic resins in the H/sup +/, Na/sup +/, Cs/sup +/, and Sr/sup +2/ forms were loaded with /sup 137/Cs and /sup 85/Sr, were mixed in different ratios with anionic resins in the SO/sub 4/ form, and were solidified in bitumen. The leachability and physical integrity of the resulting organic ion exchange resin/bitumen composites were measured. A total of 30 DOT 17H drums, from three different manufacturing lots, were tested to determine if they met the specifications set forth in the Code of Federal Regulations 49 CFR 178-118-66. The results are presented. 15 references, 39 figures, 10 tables.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6696045
- Report Number(s):
- NUREG/CR-2125; BNL-NUREG-51384; ON: DE84015919
- Resource Relation:
- Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Properties of radioactive wastes and waste containers. Quarterly progress report, July-September 1980. [Resin/bitumen composites; cement/ion exchange resin]
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42 ENGINEERING
CESIUM 137
LEACHING
COBALT 60
CONTAINERS
TESTING
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
STRONTIUM 85
BITUMENS
BORIC ACID
CARBON STEELS
CEMENTS
EXPERIMENTAL DATA
ION EXCHANGE MATERIALS
PORTLAND CEMENT
RESINS
SIMULATION
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COBALT ISOTOPES
DATA
DAYS LIVING RADIOISOTOPES
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ELECTRON CAPTURE RADIOISOTOPES
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INORGANIC ACIDS
INTERMEDIATE MASS NUCLEI
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ORGANIC COMPOUNDS
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PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
POLYMERS
PROCESSING
RADIOISOTOPES
SEPARATION PROCESSES
STEELS
STRONTIUM ISOTOPES
TAR
WASTE DISPOSAL
WASTE MANAGEMENT
WASTE PROCESSING
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