Cation exchange concentraion of the Americium product from TRUEX
Description
A transuranic extraction (TRUEX) process has been developed to separate and recover plutonium, americium, and other transuranic (TRU) elements from acid wastes. The main objective of the process is to reduce the effluent to below the TRU limit for actinide concentrations (<100 nCi/g of material) so it can be disposed of inexpensively. The process yields a dilute nitric acid stream containing low concentrations of the extracted americium product. This solution also contains residual plutonium and trace amounts of iron. The americium will be absorbed into a cation exchange resin bed to concentrate it for disposal or for future use. The overall objective of these laboratory tests was to determine the performance of the cation exchange process under expected conditions of the TRUEX process. Effects of acid, iron, and americium concentrations on americium absorption on the resin were determined. Distribution coefficients for americium absorption from acide solutions on the resin were measured using batch equilibrations. Batch equilibrations were also used to measure americium absorption in the presence of complexants. This data will be used to identify complexants and solution conditions that can be used to elute the americium from the columns. The rate of absorption was measured by passing solutions containing americium through small columns of resin, varying the flowrates, and measuring the concentrations of americium in the effluent. The rate data will be used to estimate the minimum bed size of the columns required to concentrate the americium product. 11 refs. , 10 figs., 2 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE91018144; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- WHC-SA--1171
Conference
- Title
- 15. actinide separations conference.
- Dates
- 17-21 Jun 1991.
- Place
- Charleston, SC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23012438
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ABSORPTION; AMERICIUM; CITRIC ACID; ION EXCHANGE; ION EXCHANGE MATERIALS; IRON; NITRIC ACID; PERFORMANCE; RESINS; TRUEX PROCESS
- Descriptors DEC
- ACTINIDES; CARBOXYLIC ACIDS; ELEMENTS; HYDROGEN COMPOUNDS; HYDROXY ACIDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MATERIALS; METALS; NITROGEN COMPOUNDS; ORGANIC ACIDS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; OXYGEN COMPOUNDS; POLYMERS; SEPARATION PROCESSES; TRANSITION ELEMENTS; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS
Optional Information
- Contract/Grant/Project number
- Contract AC06-87RL10930
- Funding organization
- USDOE, Washington, DC (United States).
- Secondary number(s)
- CONF-9106203--5.