Strippable coating used for the TMI-2 reactor building decontamination
Strippable coating material used in the TMI-2 reactor building decontamination has been tested for Sr, Cs, and Co leachability, for radiation stability, thermal stability, and for resistance to biodegradation. It was also immersion tested in water, a water solution saturated with toluene and xylene, toluene, xylene, and liquid scintillation counting (LSC) cocktail. Leach testing resulted in all of the Cs and Co activity and most of the Sr activity being released from the coating in just a few days. Immersion resulted in swelling of the coating in all of the liquids tested. Gamma irradiation and heating of the coating did not produce any apparent physical changes in the coating to 1 x 10/sup 8/ rad and 100/sup 0/C; however, gas generation of H/sub 2/, CO, CO/sub 2/ was observed in both cases. Biodegradation of the coating occurred readily in soils as indicated by monitoring CO/sub 2/ produced from microbial respiration. These test results indicate that strippable coating radwaste would have to be stabilized to meet the requirements for Class B waste outlined in 10 CFR Part 61 and the NRC Draft Technical Position on Waste Form.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 6925812
- Report Number(s):
- BNL-NUREG-34430; CONF-840307-29; ON: DE84010516
- Resource Relation:
- Conference: Waste management '84, Tucson, AZ, USA, 11 Mar 1984; Other Information: Portions are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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