Concentration and Final Purification of Neptunium by Anion Exchange

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Description

It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless steel corrosion products. The present specifications are for the neptunium final product to contain less than 0.1 weight percent plutonium, to be … continued below

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15 pages : illustrations

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Ryan, J.L. February 10, 1959.

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  • Main Title: Concentration and Final Purification of Neptunium by Anion Exchange
  • Series Title: HW (Series)
  • Series Title: Hanford Works Reports
  • Added Title: Hanford Works Report HW-59193

Description

It is anticipated that neptunium will be recovered in the Purex process by solvent extraction or ion exchange methods as a nitric acid solution of greater than 0.1 g. Np/1 and containing varying amounts of fission products, plutonium, uranium, and thorium, including Th234 (UX1). At the present time this solution is thermally concentrated in the Purex L-cell package to several grams of neptunium per liter. In this operation the solution is contaminated rather badly with plutonium and stainless steel corrosion products. The present specifications are for the neptunium final product to contain less than 0.1 weight percent plutonium, to be relatively free of gross metallic contaminates, and to be low enough in fission product game activity and Th234-Pa234 (UX1-UX2) beta activity to be handled without resorting to remote techniques.

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15 pages : illustrations

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  • SuDoc Number: Y 3.At 7:22/HW-59193
  • Report No.: HW-59193
  • Accession or Local Control No: metadc1255009
  • Archival Resource Key: ark:/67531/metadc1255009

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  • February 10, 1959

Added to The UNT Digital Library

  • Feb. 5, 2022, 6:49 p.m.

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  • Jan. 24, 2023, 11:29 a.m.

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Ryan, J.L. Concentration and Final Purification of Neptunium by Anion Exchange, report, February 10, 1959; Washington D.C.. (https://digital.library.unt.edu/ark:/67531/metadc1255009/: accessed March 8, 2026), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.

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