Initial demonstration of the vitrification of nuclear waste sludge containing an organic Cs-loaded ion exchange resin
When immobilizing into borosilicate glass the radionuclides in the caustic high-level radioactive wastes stored in the USA, the soluble fission product Cs-137 has to be removed from supernates of the wastes. In the current processes zeolites or an organic precipitant will be used to remove the Cs. These solids are then treated further and mixed with the radioactive sludges and vitrified into a borosilicate glass. This paper describes the vitrification of a mixture resulting from using a new process to remove Cs from the caustic supernate. An organic ion exchange resin is used. This resin was then mixed with sludge andfrit and vitrified. Using an organic ion exchange resin rather than zeolite or the organic precipitant has certain advantages. Some of these are discussed in the paper. Results in the paper indicate that a mixture of the resin, sludge and frit can be successfully vitrified in a joule-heated, slurry fed melter. The redox state of the glass is lowered by the presence of the resin in the feed, but the glass is still suitable as a canistered wasteform for radioactive waste glass.
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10127169
- Report Number(s):
- WSRC-MS-91-465; CONF-921101-92; ON: DE93006873
- Resource Relation:
- Conference: 16. Materials Research Society (MRS) fall meeting,Boston, MA (United States),30 Nov - 5 Dec 1992; Other Information: PBD: [1991]
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
SLUDGES
CHEMICAL ANALYSIS
BOROSILICATE GLASS
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
SAVANNAH RIVER PLANT
RADIOACTIVE WASTE PROCESSING
ORGANIC COMPOUNDS
ION EXCHANGE
CESIUM 137
ZEOLITES
MELTING
HYDROLYSIS
PH VALUE
RELIABILITY
REDOX REACTIONS
052001
WASTE PROCESSING