TRUEX process - a process for the extraction of the transuranic elements from nitric acid wastes utilizing modified PUREX solvent

Journal Article · Tue Jan 01 00:00:00 EST 1985 · Solvent Extr. Ion Exch.; (United States)

DOI:https://doi.org/10.1080/07366298508918504· OSTI ID:5384369

Horwitz, E P; Kalina, D G; Diamond, H; Vandegrift, G F; Schulz, W W

A generic transuranic (TRU) element extraction/recovery process was developed based on the use of octyl(phenyl)-N,N-diisobutylcarbamoylmethylphosphine oxide, O phi D(iB)CMPO, dissolved in PUREX process solvent (tributyl phosphate, TBP, in normal paraffinic hydrocarbon, NPH). The process (called TRUEX) is capable of reducing the TRU concentration by many orders of magnitude in waste solutions containing a wide range of nitric acid, salt, and fission product concentrations. A major feature of the process is that it is readily adaptable for waste processing in existing fuel reprocessing facilities.

• Research Organization: Argonne National Lab., IL
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5384369
• Journal Information: Solvent Extr. Ion Exch.; (United States), Vol. 3:1-2
• Country of Publication: United States
• Language: English

Related Subjects

37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
TRANSURANIUM ELEMENTS
SOLVENT EXTRACTION
EXPERIMENTAL DATA
HYDROCARBONS
PHOSPHINES
REPROCESSING
SPENT FUELS
TBP
BUTYL PHOSPHATES
DATA
ELEMENTS
ENERGY SOURCES
ESTERS
EXTRACTION
FUELS
INFORMATION
MATERIALS
NUCLEAR FUELS
NUMERICAL DATA
ORGANIC COMPOUNDS
ORGANIC PHOSPHORUS COMPOUNDS
PHOSPHORIC ACID ESTERS
PHOSPHORUS COMPOUNDS
REACTOR MATERIALS
SEPARATION PROCESSES
400105* - Separation Procedures
050800 - Nuclear Fuels- Spent Fuels Reprocessing