Task 3 - pyrolysis of plastic waste. Semi-annual report, April 1--September 30, 1996
This report briefly describes progress in the development of a thermal decomposition process for volume reduction of spent ion-exchange resin. During the reporting period, two series of tests were performed. The mixed waste plastics test investigated the effectiveness of the process in concentrating radionuclide surrogates in a solids residual while yielding a surrogate-free condensate product. Preliminary results indicated the occurrence of solids carryover. The ion-exchange resin tests resulted in a cesium concentration in the unfiltered condensate of about 4 to 20 micrograms/gram, indicating that fine particulate material was passing through the reactor cyclone. Future work includes the evaluation of an auger reactor in place of the fluidized bed reactor to address the problem of reactor carryover. 2 figs., 7 tabs.
- Research Organization:
- Univ. of North Dakota, Grand Forks, ND (United States). Energy and Environmental Research Center
- Sponsoring Organization:
- USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
- DOE Contract Number:
- FC21-94MC31388
- OSTI ID:
- 485945
- Report Number(s):
- DOE/MC/31388-5498; ON: DE97002177; TRN: 97:003918
- Resource Relation:
- Other Information: PBD: [1997]
- Country of Publication:
- United States
- Language:
- English
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