Optimization of solvent extraction cycles to separate plutonium and neptunium

Journal Article · Tue Sep 01 00:00:00 EDT 1998 · Transactions of the American Nuclear Society

OSTI ID:644251

Marsh, D L; Miller, L F ^[1]; Bond, W; Martin, R C; Felker, L K; Wham, R M ^[2]; Schweitzer, G K ^[1]

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1. Univ. of Tennessee, Knoxville, TN (United States)
2. Oak Ridge Y-12 Plant, TN (United States)

This paper describes the steps taken to assess the potential of a solvent extraction process for separating plutonium from neptunium. The plutonium, namely {sup 238}Pu, is of importance because it is the isotope used in making radioisotope thermoelectric generators and radioisotope heaters and is obtained by irradiating {sup 237}Np targets in a high neutron flux environment. After the neptunium targets have been irradiated, the targets could then be processed by solvent extraction methods.

• OSTI ID: 644251
• Report Number(s): CONF-980606--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 78; ISSN 0003-018X; ISSN TANSAO
• Country of Publication: United States
• Language: English

Related Subjects

07 ISOTOPE AND RADIATION SOURCES
40 CHEMISTRY
ISOTOPE PRODUCTION
NEPTUNIUM 237
NESDPS Office of Nuclear Energy Space and Defense Power Systems
PLUTONIUM 238
RADIOISOTOPE HEAT SOURCES
SOLVENT EXTRACTION
THERMOELECTRIC GENERATORS