Ion exchange technology in spent fuel reprocessing

Technical Report · Tue Jan 01 00:00:00 EST 1985

OSTI ID:6271778

Navratil, J D

Solvent extraction is the major unit operation employed in spent nuclear fuel reprocessing. The operation yields three streams: fission product waste, uranium product and plutonium product. Ion exchange is primarily used in reprocessing as a tail-end method to concentrate and isolate the plutonium product stream. This chapter will describe the details of plutonium recovery and purification by both cation and anion exchange processing. A brief overview of miscellaneous uses of ion exchange employed in reprocessing will also be given. 19 references, 6 figures, 2 tables.

• Research Organization: Rockwell International Corp., Golden, CO (USA). Rocky Flats Plant
• DOE Contract Number: AC04-76DP03533
• OSTI ID: 6271778
• Report Number(s): RFP-3639; ON: DE85003967
• Resource Relation: Other Information: Portions are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
37 INORGANIC
ORGANIC
PHYSICAL AND ANALYTICAL CHEMISTRY
PLUTONIUM
ION EXCHANGE
PURIFICATION
RECOVERY
PUREX PROCESS
SOLVENT EXTRACTION
SPENT FUELS
ACTINIDES
ELEMENTS
ENERGY SOURCES
EXTRACTION
FUELS
MATERIALS
METALS
NUCLEAR FUELS
REACTOR MATERIALS
REPROCESSING
SEPARATION PROCESSES
TRANSURANIUM ELEMENTS
050800* - Nuclear Fuels- Spent Fuels Reprocessing
400105 - Separation Procedures