Kilogram-scale purification of americium by ion exchange
Description
Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of the absorbed band down 3 to 4 successive beds of the same resin, preloaded with Zn/sup 2 +/, … continued below
Physical Description
20 pages
Creation Information
Wheelwright, E. J. January 1, 1979.
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Pacific Northwest Laboratory
Publisher Info: Battelle Pacific Northwest Labs., Richland, WA (USA)Place of Publication: Richland, Washington
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Description
Sequential anion and cation exchange processes have been used for the final purification of /sup 241/Am recovered during the reprocessing of aged plutonium metallurgical scrap. Plutonium was removed by absorption of Dowex 1, X-3.5 (30 to 50 mesh) anion exchange resin from 6.5 to 7.5 M HNO/sub 3/ feed solution. Following a water dilution to 0.75 to 1.0 M HNO/sub 3/, americium was absorbed on Dowex 50W, X-8 (50 to 100 mesh) cation exchange resion. Final purification was accomplished by elution of the absorbed band down 3 to 4 successive beds of the same resin, preloaded with Zn/sup 2 +/, with an NH/sub 4/OH buffered chelating agent. The recovery of mixed /sup 241/Am-/sup 243/Am from power reactor reprocessing waste has been demonstrated. Solvent extraction was used to recover a HNO/sub 3/ solution of mixed lanthanides and actinides from waste generated by the reprocessng of 13.5 tons of Shippingport Power Reactor blanket fuel. Sequential cation exchange band-displacement processes were then used to separate americium and curium from the lanthanides and then to separate approx. 60 g of /sup 244/Cm from 1000 g of mixed /sup 241/Am-/sup 243/Am.
Physical Description
20 pages
Notes
NTIS, PC A02/MF A01.
Subjects
Keywords
- Actinide Isotopes
- Actinide Nuclei
- Actinides
- Adsorption
- Alpha Decay Radioisotopes
- Americium
- Americium 241
- Americium 243
- Americium Isotopes
- Curium
- Curium 244
- Curium Isotopes
- Dispersions
- Elements
- Energy Sources
- Even-Even Nuclei
- Extraction
- Fuels
- Heavy Nuclei
- Hydrogen Compounds
- Inorganic Acids
- Ion Exchange
- Isotopes
- Management
- Materials
- Metals
- Mixtures
- Nitric Acid
- Nuclear Fuels
- Nuclei
- Odd-Even Nuclei
- Organic Compounds
- Organic Polymers
- Petrochemicals
- Petroleum Products
- Plutonium
- Polymers
- Processing
- Purification
- Radioactive Waste Processing
- Radioisotopes
- Rare Earths
- Reactor Materials
- Reprocessing
- Resins
- Separation Processes
- Solutions
- Solvent Extraction
- Sorption
- Spent Fuels
- Transplutonium Elements
- Transuranium Elements
- Waste Management
- Waste Processing
- Years Living Radioisotopes 050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
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Source
- Symposium on separation science and technology for energy applications, Gatlinburg, TN, USA, 30 Oct 1979
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- Report No.: PNL-SA-7844
- Report No.: CONF-7910108-4
- Grant Number: EY-76-C-06-1830
- Office of Scientific & Technical Information Report Number: 5381944
- Archival Resource Key: ark:/67531/metadc1063914
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- January 1, 1979
Added to The UNT Digital Library
- Feb. 4, 2018, 10:51 a.m.
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- Aug. 6, 2019, 12:48 p.m.
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Wheelwright, E. J. Kilogram-scale purification of americium by ion exchange, article, January 1, 1979; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1063914/: accessed July 16, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.