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U.S. Department of Energy
Office of Scientific and Technical Information

Properties of radioactive wastes and waste containers. Quarterly progress report, April-June 1980

Technical Report ·
DOI:https://doi.org/10.2172/5128637· OSTI ID:5128637

A study was initiated to determine the effect of varying V/S (the ratio of the waste form volume to its surface area) on the leachability of radioisotopes incorported in cement forms. Cesium-137 and strontium-85 mixed with a simulated formulation of waste derived from forced recirculation evaporator bottoms of LWR's were solidified in portland II cement. The V/S ratios of the forms varied from 0.41 to 2.77. The resulting forms were leached using a modified IAEA procedure. Leaching data indicate an inverse relationship between the amount of leached radioactivity and V/S value. Experiments were undertaken to determine the degree of desorption of Cs-137 initially adsorbed on cation organic ion exchange resins upon mixing with cement paste and during the plastic phase of the curing process. Portland II and lumnite cements were used as the solidification agents. Twenty seven percent of the Cs-137 was removed from the ion exchange resins after two hours of contact with portland II cement, whereas, 43% of the activity was removed from the resins after the same contact period with lumnite cement. 15 refs., 12 figs., 4 tabs.

Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5128637
Report Number(s):
NUREG/CR-1694; BNL-NUREG-51266; ON: TI86002662
Country of Publication:
United States
Language:
English