Offgas Emissions from the Vitrification of Hanford Envelope C Low Activity Waste
A sample of radioactive waste from Hanford tank 241-AN-102, pretreated to remove undissolved solids, 137Cs, 90Sr, 99Tc, and transuranic elements, was melted in a bench-scale melter to produce a vitrified waste form. The pretreated waste was mixed with glass forming chemicals to give a slurry feed for the melter. Measurements of fixed gas, volatile metal, and particulate offgas emissions were performed. Only small amounts of flammable gases H2 and CO were formed. The metals and radionuclides with the highest emissions were the more volatile metals, as expected. The more volatile species were B, Na, K, 99Tc, and 137Cs. Boron, 99Tc, and 137Cs evolved at higher rates during idling of the melter that during feeding the slurry. The composition of the particulate emissions approximated the composition of the feed.
- Research Organization:
- Savannah River Site (SRS), Aiken, SC (United States)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- AC09-96SR18500
- OSTI ID:
- 807674
- Report Number(s):
- WSRC-MS-2003-00072; TRN: US0301947
- Resource Relation:
- Conference: International Conference on Thermal Treatment Technology, Orlando, FL (US), 05/12/2003--05/16/2003; Other Information: PBD: 6 Feb 2003
- Country of Publication:
- United States
- Language:
- English
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