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
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container_title J. Nucl. Sci. Technol. (Tokyo), 6: 285-9(May 1969)
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creator AKATSU, Johkun
description 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.
doi_str_mv 10.1080/18811248.1969.9732884
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1881-1248
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source J-STAGE Free; EZB-FREE-00999 freely available EZB journals; Alma/SFX Local Collection; Free Full-Text Journals in Chemistry
subjects 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
title Mutual Separation of U, Pu and Fission Products with Tri-iso-octylamine
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