Solidification of ion exchange resin wastes

Technical Report · Sun Aug 01 00:00:00 EDT 1982

DOI:https://doi.org/10.2172/6794443· OSTI ID:6794443

Solidification media investigated included portland type I, portland type III and high alumina cements, a proprietary gypsum-based polymer modified cement, and a vinyl ester-styrene thermosetting plastic. Samples formulated with hydraulic cement were analyzed to investigate the effects of resin type, resin loading, waste-to-cement ratio, and water-to-cement ratio. The solidification of cation resin wastes with portland cement was characterized by excessive swelling and cracking of waste forms, both after curing and during immersion testing. Mixed bed resin waste formulations were limited by their cation component. Additives to improve the mechanical properties of portland cement-ion exchange resin waste forms were evaluated. High alumina cement formulations dislayed a resistance to deterioration of mechanical integrity during immersion testing, thus providing a significant advantage over portland cements for the solidification of resin wastes. Properties of cement-ion exchange resin waste forms were examined. An experiment was conducted to study the leachability of /sup 137/Cs, /sup 85/Sr, and /sup 60/Co from resins modified in portland type III and high alumina cements. The cumulative /sup 137/Cs fraction release was at least an order of magnitude greater than that of either /sup 85/Sr or /sup 60/Co. Release rates of /sup 137/Cs in high alumina cement were greater than those in portland III cement by a factor of two.Compressive strength and leach testing were conducted for resin wastes solidified with polymer-modified gypsum based cement. /sup 137/Cs, /sup 85/Sr, and /sup 60/Co fraction releases were about one, two and three orders of magnitude higher, respectively, than in equivalent portland type III cement formulations. As much as 28.6 wt % dry ion exchange resin was successfully solidified using vinyl ester-styrene compared with a maximum of 25 wt % in both portland and gypsum-based cement.

• Research Organization: Brookhaven National Lab. (BNL), Upton, NY (United States)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6794443
• Report Number(s): BNL-51615; ON: DE83005949
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
CESIUM 137
LEACHING
COBALT 60
RADIOACTIVE WASTE PROCESSING
LOW-LEVEL RADIOACTIVE WASTES
SOLIDIFICATION
STRONTIUM 85
ADDITIVES
ALUMINIUM OXIDES
CEMENTS
COMPRESSION STRENGTH
EXPERIMENTAL DATA
GYPSUM CEMENTS
ION EXCHANGE MATERIALS
PLASTICS
POLYMERS
PORTLAND CEMENT
QUANTITY RATIO
RADIATION EFFECTS
RESINS
VINYL MONOMERS
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
ALUMINIUM COMPOUNDS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CESIUM ISOTOPES
CHALCOGENIDES
COBALT ISOTOPES
DATA
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
HOURS LIVING RADIOISOTOPES
INFORMATION
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
MONOMERS
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
ORGANIC COMPOUNDS
ORGANIC POLYMERS
OXIDES
OXYGEN COMPOUNDS
PETROCHEMICALS
PETROLEUM PRODUCTS
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
SEPARATION PROCESSES
STRONTIUM ISOTOPES
SYNTHETIC MATERIALS
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
YEARS LIVING RADIOISOTOPES
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