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AN ANALYTICAL METHOD FOR NEPTUNIUM-237 USING ANION EXCHANGE

Technical Report ·
DOI:https://doi.org/10.2172/4267475· OSTI ID:4267475

A method was developed for separation of neptunium from plutonium, uraniiun, americium, curium, and fission products by anion exchange with sufficient decontamination to permit neptanium-237 estimation by alpha energy analysis and neptanium-239 estimation by gamma spectrometry. The sample is spiked with neptunium-239 tracer to permit yield corrections and loaded on a small column of Dowex 1, X-4 (100-200 mesh) from 8 M nitric acid in the presence of ferrous sulfamate and semicarbazide. After washing the resin with 30 to 40 column volumes of a 4.5 M nitric acid solution containing ferrous sulfamate and semicarbazide, the neptunium is eluted with 0.005 M ceric sulfate in dilute nitric acid and mounted for total alpha counting, alpha energy analysis, and gamma energy analysis. Neptunium recoveries of 95% have been obtained while plutonium decontamination factors are 5 x 10/sup 4/. Decontamination factors for uranium americium, curium, and gross fission products are all greater than 10/sup 4/. Uranium, up to 180 g/l in the column feed, does not interfere. The plutonium decontamination factor can be increased by a factor of 10 to 100 by fol lowing the nitric acid-ferrous sulfamate-semicarbazide wash by a wash with 0.1 M NH/sub 4/I in 12 M HCl. This is followed by neptunium elution with 6.5 M HCl containing 0.004 M HF. The method is applicable to the high salt samples from the Redox process as well as Purex process samples. (auth)

Research Organization:
General Electric Co. Hanford Atomic Products Operation, Richland, Wash.
Sponsoring Organization:
USDOE
DOE Contract Number:
W-31-109-ENG-52
NSA Number:
NSA-13-012431
OSTI ID:
4267475
Report Number(s):
HW-59032
Country of Publication:
United States
Language:
English