Separation of Plutonium-238 from Fission Products by Solvent Extraction Using HDEHP

A procedure for separating 238 Pu from a Np sample irradiated with neutrons is described. Rapid separation of Pu by HDEHP solvent extraction was attempted, and without adjusting its valency states in the dissolver solution of the sample. Both Pu(IV) and Pu(VI) were extracted along with Np from the H...

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Veröffentlicht in:	J. Nucl. Sci. Technol. (Tokyo), v. 10, no. 11, pp. 696-699 v. 10, no. 11, pp. 696-699, 1973-11, Vol.10 (11), p.696-699
1. Verfasser:	AKATSU, Johkun
Format:	Artikel
Sprache:	eng
Schlagworte:	CATIONS DECONTAMINATION decontamination factor fission products FISSION PRODUCTS- SOLVENT EXTRACTION HDEHP IRRADIATION mass spectrometry N40440 -Chemistry-Radiochemistry & Nuclear Chemistry- Radioisotope Production NEPTUNIUM OXIDES NESDPS Office of Nuclear Energy Space and Defense Power Systems NEUTRON BEAMS NITRIC ACID plutonium 238 PLUTONIUM 238- ISOTOPE PRODUCTION PLUTONIUM COMPOUNDS PLUTONIUM NITRATES PLUTONIUM- SOLVENT EXTRACTION separation process solvent extraction valency state
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Zusammenfassung:	A procedure for separating 238 Pu from a Np sample irradiated with neutrons is described. Rapid separation of Pu by HDEHP solvent extraction was attempted, and without adjusting its valency states in the dissolver solution of the sample. Both Pu(IV) and Pu(VI) were extracted along with Np from the HNO 3 solutions of various concentrations. The Pu and Np extracted in the organic solution were back-extracted with oxalic acid solutions. The decontamination factors of the crude products were of the order of 10 2 for gross γ-activity. The Pu in the products was separated from Np by means of ion exchange resin columns. Approximately 0.5 mg of 238 Pu was obtained with an efficiency exceeding 95%.
ISSN:	0022-3131 1881-1248
DOI:	10.1080/18811248.1973.9735475