Published February 1986
| Version v1
Report
Ion exchange technology in spent fuel reprocessing
Description
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 tailend 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. (author)
Additional details
Publishing Information
- Imprint Title
- Ion exchange technology in the nuclear fuel cycle
- Imprint Pagination
- 245 p.
- Journal Page Range
- p. 177-196.
- Report number
- IAEA-TECDOC--365
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 17054132
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- DISTRIBUTION FUNCTIONS; FISSION PRODUCTS; ION EXCHANGE; ION EXCHANGE CHROMATOGRAPHY; PLUTONIUM NITRATES; PUREX PROCESS; PURIFICATION; QUANTITY RATIO; RESINS; SPENT FUELS; URANIUM NITRATES
- Descriptors DEC
- ACTINIDE COMPOUNDS; CHROMATOGRAPHY; ENERGY SOURCES; FUELS; ISOTOPES; MATERIALS; NITRATES; NITROGEN COMPOUNDS; NUCLEAR FUELS; ORGANIC COMPOUNDS; ORGANIC POLYMERS; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; POLYMERS; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REPROCESSING; SEPARATION PROCESSES; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS
Optional Information
- Notes
- 20 refs, 6 figs, 2 tabs.