Apparatus and method for reprocessing and separating spent nuclear fuels
Description
A method and apparatus for separating and reprocessing spent nuclear fuels includes a separation vessel housing a molten metal solvent in a reaction region, a reflux region positioned above and adjacent to the reaction region, and a porous filter member defining the bottom of the separation vessel in a supporting relationship with the metal solvent. Spent fuels are added to the metal solvent. A non-oxidizing nitrogen-containing gas is introduced into the separation vessel, forming solid actinide nitrides in the metal solvent from actinide fuels, while leaving other fission products in solution. A pressure of about 1.1 to 1.2 atm is applied in the reflux region, forcing the molten metal solvent and soluble fission products out of the vessel, while leaving the solid actinide nitrides in the separation vessel. (author)
Availability note (English)
MF available from INIS under the Report Number.Files
15024196.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 7 p.
- IPC:
- Int. Cl. G21c19/48; C01b21/06.
- IPC
- Int. Cl. G21c19/48; C01b21/06.
- Patent number
- GB patent document 2113901/A/
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 15024196
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- ACTINIDE COMPOUNDS; CHEMICAL REACTIONS; CONTAINERS; DISTILLATION; FILTERS; FISSION PRODUCTS; LIQUID METALS; MEDIUM PRESSURE; NITRIDES; NITROGEN; REPROCESSING; SOLIDS; SOLUBILITY; SOLUTIONS; SOLVENTS; SPENT FUELS; VOLATILITY
- Descriptors DEC
- DISPERSIONS; ELEMENTS; ENERGY SOURCES; FLUIDS; FUELS; HOMOGENEOUS MIXTURES; ISOTOPES; LIQUIDS; MATERIALS; METALS; MIXTURES; NITROGEN COMPOUNDS; NONMETALS; NUCLEAR FUELS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; SEPARATION PROCESSES
Optional Information
- Secondary number(s)
- US priority 340591.