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Title: Solidification of commercial and defense low-level radioactive waste in polyethylene

Conference ·
OSTI ID:5948028

A process was developed for the solidification of salt wastes, incinerator ash and ion-exchange resins in polyethylene. Of the salt wastes, sodium sulfate and boric acid are representative of the wastes produced at commercial nuclear facilities while sodium nitrate in a typical high-volume waste generated at defense-related facilities. Ease of processibility and high loading efficiencies were obtained through the use of low-density polyethylene with melt indices ranging from 2.0 to 55.0 g/minute. The process utilized a commercially available single-screw extruder to incorporate the wastes into the polyethylene at about 120/sup 0/C to produce a homogeneous mixture. Although present studies utilize dry wastes, wet wastes can also be processed using vented extruders of the type used commercially for the bitumen solidification process. Tests were performed on the waste forms to determine leachability and mechanical properties. To confirm the compatibility of polyethylene and nitrate salt waste at elevated temperatures, the self-ignition temperatures were measured and a differential scanning calorimeter was used to characterize the thermal behavior of oxidizing compounds contained in the simulated waste, as well as the real Savannah River Plant waste. No exothermic reactions were observed over the temperature range studied from 50/sup 0/C to 400/sup 0/C. 18 refs., 7 figs., 8 tabs.

Research Organization:
Brookhaven National Lab., Upton, NY (USA)
DOE Contract Number:
AC02-76CH00016
OSTI ID:
5948028
Report Number(s):
BNL-40350; CONF-870859-22; ON: DE88001553; TRN: 87-040211
Resource Relation:
Conference: 9. annual low-level radioactive waste management program conference, Denver, CO, USA, 25 Aug 1987; Other Information: Portions of this document are illegible in microfiche products
Country of Publication:
United States
Language:
English