Solidification of ion exchange resin wastes in hydraulic cement
Work has been conducted to investigate the solidification of ion exchange resin wastes with portland cements. These efforts have been directed toward the development of acceptable formulations for the solidification of ion exchange resin wastes and the characterization of the resultant waste forms. This paper describes formulation development work and defines acceptable formulations in terms of ternary phase compositional diagrams. The effects of cement type, resin type, resin loading, waste/cement ratio and water/cement ratio are described. The leachability of unsolidified and solidified resin waste forms and its relationship to full-scale waste form behavior is discussed. Gamma irradiation was found to improve waste form integrity, apparently as a result of increased resin crosslinking. Modifications to improve waste form integrity are described. 3 tables.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5169950
- Report Number(s):
- BNL-31592; CONF-820424-32; ON: DE82018064
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
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BUILDING MATERIALS
CEMENTS
COOLANT CLEANUP SYSTEMS
COOLING SYSTEMS
CURING
DISSOLUTION
ELECTROMAGNETIC RADIATION
ENERGY SYSTEMS
GAMMA RADIATION
ION EXCHANGE MATERIALS
IONIZING RADIATIONS
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MANAGEMENT
MATERIALS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
ORGANIC COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
POLYMERS
PORTLAND CEMENT
POWER PLANTS
PRIMARY COOLANT CIRCUITS
PROCESSING
RADIATION EFFECTS
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
RESINS
SEPARATION PROCESSES
SIMULATION
SOLIDIFICATION
THERMAL POWER PLANTS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES