Mutual Separation of U, Pu and Fission Products with Tri-iso-octylamine

Uranium and Pu were extracted with tri-wo-octylamine (CC1 4 ) from irradiated U dissolved in sulfuric acid, from which Pu was back-extracted with sulfurous acid, and U with I M NH 4 AC-1.5%H 2 O 2 . The decontamination factors were estimated to be 10 2 for U fraction (γ and β) activities) and >10...

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Veröffentlicht in:	J. Nucl. Sci. Technol. (Tokyo), 6: 285-9(May 1969) 6: 285-9(May 1969), 1969-05, Vol.6 (5), p.285-289
1. Verfasser:	AKATSU, Johkun
Format:	Artikel
Sprache:	eng
Schlagworte:	ALKYL RADICALS AMINES EFFICIENCY FISSION PRODUCTS FISSION PRODUCTS/separation of plutonium and uranium from, by solvent extraction using triisooctylamine N20510 -Chemistry-Radiochemistry & Nuclear Chemistry- Reactor Fuel Processing OCTYL RADICALS PLUTONIUM PLUTONIUM/separation from irradiated uranium dissolved in sulfuric acid by solvent extraction using triisooctylamine SEPARATION PROCESSES SOLVENT EXTRACTION SULFURIC ACID TOA TRIISOOCTYLAMINE/solvent properties for plutonium and uranium URANIUM URANIUM/separation from irradiated uranium dissolved in sulfuric acid by solvent extraction using triisooctylamine
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Beschreibung
Zusammenfassung:	Uranium and Pu were extracted with tri-wo-octylamine (CC1 4 ) from irradiated U dissolved in sulfuric acid, from which Pu was back-extracted with sulfurous acid, and U with I M NH 4 AC-1.5%H 2 O 2 . The decontamination factors were estimated to be 10 2 for U fraction (γ and β) activities) and >10 3 for Pu fraction.
ISSN:	0022-3131 1881-1248
DOI:	10.1080/18811248.1969.9732884