TRUEX Processing of Plutonium Analytical Solutions at Argonne National Laboratory

Autor:	George F. Vandegrift, R. A. Leonard, D. B. Chamberlain, D.G. Wygmans, Joseph C. Hutter, C. Conner
Rok vydání:	1997
Předmět:	Process Chemistry and Technology General Chemical Engineering Radiochemistry chemistry.chemical_element Radioactive waste Filtration and Separation Americium General Chemistry Raffinate Actinide Uranium Plutonium Waste treatment chemistry Liquid–liquid extraction
Zdroj:	Separation Science and Technology. 32:303-326
ISSN:	1520-5754 0149-6395
DOI:	10.1080/01496399708003201
Popis:	The TRUEX (TRansUranic EXtraction) solvent extraction process was developed at Argonne National Laboratory (ANL) for the Department of Energy. A TRUEX demonstration completed at ANL involved the processing of analytical and experimental waste generated there and at the New Brunswick Laboratory. A 20-stage centrifugal contactor was used to recover plutonium, americium, and uranium from the waste. Approximately 84 g of plutonium, 18 g of uranium, and 0.2 g of americium were recovered from about 118 L of solution during four process runs. Alpha decontamination factors as high as 65,000 were attained, which was especially important because it allowed the disposal of the process raffinate as a lowlevel waste. The recovered plutonium and uranium were converted to oxide; the recovered americium solution was concentrated by evaporation to approximately 100 mL. The flowsheet and operational procedures were modified to overcome process difficulties. These difficulties included the presence of complexants i...
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::f12eeb158db72db97e76d7b9f7161a52 https://doi.org/10.1080/01496399708003201 Zobrazit plný text záznamu