Properties of radioactive wastes and waste containers. Quarterly progress report, July-September 1980. [Resin/bitumen composites; cement/ion exchange resin]
A study was initiated to evaluate the leachability and integrity of bitumen/organic ion exchange resin composites. Mixtures of anionic and cationic resins in the SO/sub 4//sup -2/, H/sup +/, Cs/sup +/, and Sr/sup +2/ forms were used. The leachability of sodium and cesium from the bitumen/organic ion exchange resin composites was observed to increase when anionic resins in the sulfate form were incorporated in the composite. Topical application of a coat of bitumen on these composites decreased Na leachability by sixfold. The leachability of cesium-137 from cement waste forms and cement/organic ion exchange resin (H/sup +/ form) was studied. Portland II and lumnite cements were used in making the forms. Cesium-137 was leached at a faster rate from portland II/ion exchange resin composites that contained the higher ratio of cement to resins, and also from portland II cement waste forms than from that were made with lumnite cement. An experiment was initiated to study the volumetric changes of organic ion exchange resin beds in aquwous media as a function of ionic species and their concentrations in an aqueous milieu. The species studied were cesium, strontium, and aluminum. The resin volumes were observed to decrease when the solute ionic concentration increased, and a hysteresis effect was observed when the solute concentration was then decreased. The resin bed volumes were observed to increase as the solute concentrations decreased, but the resin volumes did not return to their original values. This observed shrinking and swelling is used to explain the disintegration of cement/organic ion exchange resin composites when immersed in water. The paper on ''Radiation effects on ion exchangers used in radioactive waste management'' in Appendix A has been processed separately for inclusion in the Energy Data Base. 18 refs., 15 figs., 13 tabs.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5188089
- Report Number(s):
- NUREG/CR-1863; BNL-NUREG-51316; ON: TI86000903
- Country of Publication:
- United States
- Language:
- English
Similar Records
Properties of radioactive wastes and waste containers. Status report, October 1980-September 1981
Properties of radioactive wastes and waste containers. Quarterly progress report, April-June 1980
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CESIUM
LEACHING
CESIUM 137
ORGANIC ION EXCHANGERS
CHEMICAL RADIATION EFFECTS
SHRINKAGE
SWELLING
RESINS
SODIUM
WASTE FORMS
ALUMINIUM
AQUEOUS SOLUTIONS
BITUMENS
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