Published March 19, 1978
| Version v1
Report
Batch extraction and stripping tests with uranium and plutonium
Description
Batch extraction tests with 30% TBP and highly irradiated LWR fuel show that losses of both U and Pu to the aqueous raffinate can be well below 0.01% of the feed. Stripping of highly loaded TBP with dilute HNO3 resulted in equally good recoveries from the organic, but the distribution coefficient (DC) for Pu increased significantly after >99% had been stripped. With long contact time during extraction (very high radiation exposure) there was essentially no change in behavior. Stripping of Pu from TBP loaded with U to <20% of saturation was much less effective, a major fraction of the Pu having a DC of about 102. Aging the loaded organic before stripping increased the fraction of Pu that was more difficult to strip. 3 figures
Additional details
Publishing Information
- Imprint Title
- Back end of the LWR fuel cycle
- Journal Page Range
- p. V.1-V.5.
- Report number
- CONF-780304--
Conference
- Title
- Back end of the LWR fuel cycle.
- Acronym
- ANS
- Dates
- 19 - 22 Mar 1978.
- Place
- Savannah, GA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 10448017
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AGING; NITRIC ACID; OCONEE-1 REACTOR; PLUTONIUM; REPROCESSING; ROBINSON-2 REACTOR; SOLVENT EXTRACTION; SPENT FUELS; URANIUM
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; METALS; NITROGEN COMPOUNDS; NUCLEAR FUELS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR MATERIALS; REACTORS; SEPARATION PROCESSES; TRANSURANIUM ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS