Pyrochemical investigations into recovering plutonium from americium extraction salt residues

Technical Report · Fri May 01 00:00:00 EDT 1987

DOI:https://doi.org/10.2172/6388919· OSTI ID:6388919

Fife, K W; West, M H

Progress into developing a pyrochemical technique for separating and recovering plutonium from spent americium extraction waste salts has concentrated on selective chemical reduction with lanthanum metal and calcium metal and on the solvent extraction of americium with calcium metal. Both techniques are effective for recovering plutonium from the waste salt, although neither appears suitable as a separation technique for recycling a plutonium stream back to mainline purification processes. 17 refs., 13 figs., 2 tabs.

• Research Organization: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6388919
• Report Number(s): LA-10963-MS; ON: DE87009486; TRN: 87-023176
• Resource Relation: Other Information: Portions of this document are illegible in microfiche products. Original copy available until stock is exhausted
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AMERICIUM 241
SOLVENT EXTRACTION
PLUTONIUM
MATERIALS RECOVERY
MOLTEN SALTS
PYROCHEMICAL REPROCESSING
REDUCTION
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
AMERICIUM ISOTOPES
CHEMICAL REACTIONS
ELEMENTS
EXTRACTION
HEAVY NUCLEI
ISOTOPES
MANAGEMENT
METALS
NUCLEI
ODD-EVEN NUCLEI
PROCESSING
RADIOISOTOPES
RECOVERY
REPROCESSING
SALTS
SEPARATION PROCESSES
TRANSURANIUM ELEMENTS
WASTE MANAGEMENT
WASTE PROCESSING
YEARS LIVING RADIOISOTOPES
050800* - Nuclear Fuels- Spent Fuels Reprocessing