Study on the technique of spent fuel reprocessing with supercritical fluid direct extraction method (Super-DIREX method)
- 1. Mitsubishi Heavy Industries Ltd., Kobe, Hyogo (Japan)
- 2. Mitsubishi Heavy Industries Ltd., Takasago, Hyogo (Japan)
- 3. Nuclear Development Corp., Tokai, Ibaraki (Japan)
- 4. Mitsubishi Heavy Industries Ltd., Yokohama, Kanagawa (Japan)
Description
The spent fuel reprocessing method with supercritical fluid has been developed. Uranium and plutonium elements can be extracted directly from spent fuel oxides by supercritical carbon dioxide (CO2) containing nitric acid and tributylphosphate (HNO3-TBP) complex at 313-333K and 10-20 MPa. It is called Super-DIREX method which stands for Supercritical fluid Direct Extraction method. In Super-DIREX method, the process from dissolution to extraction(co-decontamination) in PUREX is consolidated to one component of direct extraction column', so that the cost of the spent fuel reprocessing plant is expected to be reduced from purex process. In order to evaluate the ability of extraction, basic tests have been carried out using unirradiated uranium oxide with artificial fission products (FPs) oxide. The concentration of uranium extracted in supercritical fluid and the decontamination factor (DF) of the FPs were evaluated. The test results revealed that it would be possible to extract U selectively from the U-oxide. The DFs of almost all FPs were more than 102. The concentration of uranium extracted is approx. 4.5 g/L-scCO2 under 313K of temperature and 12 MPa of pressure. An increase of pressure may improve the concentration of uranium extracted. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875577Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of actinide 2001 international conference
- Imprint Pagination
- 986 p.
- Journal Page Range
- p. 757-760
Conference
- Title
- Actinide 2001 international conference
- Dates
- 4-9 Nov 2001
- Place
- Hayama, Kanagawa (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51054815
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CARBON DIOXIDE; FEASIBILITY STUDIES; MATERIALS RECOVERY; NITRIC ACID; REPROCESSING; SUPERCRITICAL GAS EXTRACTION; TBP; URANIUM; URANIUM OXIDES U3O8
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; BUTYL PHOSPHATES; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; ELEMENTS; ESTERS; EXTRACTION; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; MANAGEMENT; METALS; NITROGEN COMPOUNDS; ORGANIC COMPOUNDS; ORGANIC PHOSPHORUS COMPOUNDS; OXIDES; OXYGEN COMPOUNDS; PHOSPHORIC ACID ESTERS; PROCESSING; SEPARATION PROCESSES; SOLVENT EXTRACTION; URANIUM COMPOUNDS; URANIUM OXIDES; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Notes
- 16 refs., 4 figs., 1 tab.; This record replaces 34040107