Processing of tetraphenylborate precipitates in the Savannah River Site Defense Waste Processing Facility
Description
The Savannah River Site has generated 77 million gallons of high level radioactive waste since the early 1950's. By 1987, evaporation had reduced the concentration of the waste inventory to 35 million gallons. Currently, the wastes reside in large underground tanks as a soluble fraction stored, crystallized salts, and an insoluble fraction, sludge, which consists of hydrated transition metal oxides. The bulk of the radionuclides, 67 percent, are in the sludge while the crystallized salts and supernate are composed of the nitrates, nitrites, sulfates and hydroxides of sodium, potassium, and cesium. The principal radionuclide in the soluble waste is 137Cs with traces of 90Sr. The transformation of the high level wastes into a borosilicate glass suitable for permanent disposal is the goal of the Defense Waste Processing Facility (DWPF). To minimize the volume of glass produced, the soluble fraction of the waste is treated with sodium tetraphenylborate and sodium titanate in the waste tanks to precipitate the radioactive cesium ion and absorb the radioactive strontium ion. The precipitate is washed in the waste tanks and is then pumped to the DWPF. The precipitate, as received, is incompatible with the vitrification process because of the high aromatic carbon content and requires further chemical treatment. Within the DWPF, the precipitate is processed in the Salt Processing Cell to remove the aromatic carbon as benzene. The precipitate hydrolysis process hydrolyzes the tetraphenylborate anion to produce borate anion and benzene. The benzene is removed by distillation, decontaminated and transferred out of the DWPF for disposal
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92010187; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- WSRC-MS--90-162
Conference
- Title
- 200. American Chemical Society (ACS) national meeting.
- Dates
- 26-31 Aug 1990.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059947
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S61: RADIATION PROTECTION AND DOSIMETRY; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORPTION; BENZENE; BORATES; CESIUM IONS; FORMIC ACID; HIGH-LEVEL RADIOACTIVE WASTES; HYDROXYLAMINE; NITRITES; PRECIPITATION; REMOVAL; SAFETY STANDARDS; SAVANNAH RIVER PLANT; STRONTIUM IONS; TITANATES
- Descriptors DEC
- AMINES; AROMATICS; BORON COMPOUNDS; CARBOXYLIC ACIDS; CHARGED PARTICLES; HYDROCARBONS; IONS; MATERIALS; MONOCARBOXYLIC ACIDS; NATIONAL ORGANIZATIONS; NITROGEN COMPOUNDS; ORGANIC ACIDS; ORGANIC COMPOUNDS; OXYGEN COMPOUNDS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; SEPARATION PROCESSES; SORPTION; STANDARDS; TITANIUM COMPOUNDS; TRANSITION ELEMENT COMPOUNDS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; WASTES
Optional Information
- Contract/Grant/Project number
- Contract AC09-89SR18035
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-900802--21.