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Reactions Affecting Strontium Removal from Radioactive Wastes

Journal Article · · Health Physics

Alumina powder with an exchange capacity of about 1 meq/100 g removed as much strontium as a montmorillonite sample with 91 meq/100 g capacity when tested in a simulated waste solution of 0.1M NaNO3 containing 1.1 x 10-5M Sr(NO3)2and in a basic pH. Additions of orthophosphate to the simulated waste solution resulted in improved strontium removal by CaCO3 powder. With 5000 ppm of orthophosphate, 0.5 g of CaCO3 removed over 99% of the strontium from 50 cm3 of simulated waste adjusted to pH 9. Under the same test conditions, natural vermiculite showed improvement, but sodium- saturated verraiculite showed a reduction in strontium removal. By pretreating verraiculite with solutions of NaCl and NaCl-- NaOH, the mineral's affinity for strontium was improved, and an increase from 35 to 55% removal was obtained using a 0.5 g sorbent/50 ml solution ratio. From the slurry tests four possible mechanisnrs for removing strontium from radioactive wastes are suggested. These are: ion exchange as an absorption process exemplified by vermiculite, clinoptilolite, and the clay minerals; ion exchange as an adsorption process characterized by alumina and possibly variscite; metasoniatic replacement as characterized by the CaCO3-phosphate waste reaction; and precipitation reactions as evidenced by natural vermiculite in contact with phosphated waste.

Research Organization:
Oak Ridge National Lab., Tenn.
Sponsoring Organization:
USDOE
NSA Number:
NSA-17-036999
OSTI ID:
4647802
Journal Information:
Health Physics, Journal Name: Health Physics Journal Issue: 7 Vol. 9; ISSN 0017-9078
Publisher:
Health Physics Society
Country of Publication:
Country unknown/Code not available
Language:
English