Generation of equilibrium data for diluent wash flowsheet development relevant to nuclear fuel reprocessing
- 1. Reprocessing Research and Development Division, Indira Gandhi Centre for Atomic Research, Kalpakkam (India)
Description
In the PUREX process for the recovery of uranium and plutonium from spent nuclear fuel by solvent extraction employing tributylphosphate (TBP) as the solvent diluted with n-dodecane (n-DD), all the aqueous streams exiting the solvent extraction cycles are always associated with some dissolved organics. Subsequently during the evaporation of these aqueous streams for their volume reduction for better waste management, the dissolved organics pose serious safety hazards as they can lead violent runaway reactions at elevated temperatures in the presence of nitric acid which may lead to red oil explosion. Diluent wash is one of the effective methods to remove the dissolved organics from the aqueous streams. For commercial spent nuclear fuel reprocessing, it is desirable to operate this process on a continuous mode for various known advantages. The basic requirement of designing this continuous process flowsheet is the process equilibrium data. Hence experiments were carried out to generate the equilibrium data for designing a continuous diluent wash process flowsheet relevant to spent nuclear fuel reprocessing, for FBRs in particular. The data were generated in the absence of any metal ion which is very conservative to start with as presence of any of them will only lead to further reduced solubility of TBP in nitric acid stream
Additional details
Publishing Information
- Publisher
- Indian Institute of Technology Guwahati
- Imprint Place
- Guwahati (India)
- Imprint Title
- Proceedings of the seventh DAE-BRNS biennial symposium on emerging trends in separation science and technology
- Imprint Pagination
- 280 p.
- Journal Page Range
- p. 43
Conference
- Title
- 7. DAE-BRNS biennial symposium on emerging trends in separation science and technology
- Acronym
- SESTEC-2016
- Dates
- 17-20 May 2016
- Place
- Guwahati (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 47086189
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DODECANE; MATERIALS RECOVERY; NITRIC ACID; PLUTONIUM; RADIOACTIVE WASTE MANAGEMENT; SPENT FUELS; TBP; URANIUM
- Descriptors DEC
- ACTINIDES; ALKANES; BUTYL PHOSPHATES; ELEMENTS; ENERGY SOURCES; ESTERS; FUELS; HYDROCARBONS; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MANAGEMENT; MATERIALS; METALS; NITROGEN COMPOUNDS; NUCLEAR FUELS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXYGEN COMPOUNDS; PHOSPHORIC ACID ESTERS; PROCESSING; REACTOR MATERIALS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- 2 refs., 2 figs.