RECOVERY OF Np$sup 237$ BY THE NEPTEX SOLVENT-EXTRACTION PROCESS

Technical Report · Sun Mar 31 23:00:00 EST 1957

DOI:https://doi.org/10.2172/4258440· OSTI ID:4258440

Flanary, J R; Goode, J H; Mansfield, R G; Wischow, R P

Flowsheets are presented for the solvent extraction recovery of uranium and Np/sup 237/ from special highly irradiated MTR fuel elements and from nonvolatile fluoride residues from the Oak Ridge Gaseous Diffusion Plant. In both cases the material containing the neptunium and uranium is dissolved and digested to inactivate emulsion-forming impurities, the neptunium and uranium are extracted with tributyl phosphate solvent, using aluminum nitrate as the primary salting agent, scrubbed free of fission products and/or ionic contaminants, and finally separated and recovered by selective stripping with nitric acid. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-13-012541
• OSTI ID: 4258440
• Report Number(s): ORNL-2235
• Country of Publication: United States
• Language: English

Related Subjects

ALUMINUM NITRATES
BUTYL PHOSPHATES
CHEMICAL REACTIONS
CHEMISTRY
DIAGRAMS
DIFFUSION
EMULSIONS
FISSION PRODUCTS
FUEL ELEMENTS
GASES
IMPURITIES
IONS
ISOTOPE SEPARATION
MTR
NEPTEX PROCESS
NEPTUNIUM 237
NEPTUNIUM COMPOUNDS
NITRIC ACID
OPERATION
PRECIPITATION
RADIOCHEMISTRY
RECOVERY
REPROCESSING
RESEARCH REACTORS
RESIDUES
SOLUBILITY
SOLUTIONS
SOLVENT EXTRACTION
TENNESSEE
URANIUM
URANIUM COMPOUNDS
USES
VARIATIONS
VOLATILITY
WATER