Oxidation and extraction of Am(VI) using a monoamidic extractant in 3D printed centrifugal contactors
Creators
- 1. Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Description
In this study, a series of tests were performed using centrifugal contactors to evaluate the separation of Am(VI) from cerium, as well as to determine the efficiency of the contactors. All experiments were performed using 2-cm, acrylic 3D-printed centrifugal contactors. Solvent extraction tests were performed using 1 M N,N-di(2-ethylhexyl)butyramide (DEHBA)/dodecane and a nitric acid feed solution spiked with 243Am and 139Ce and oxidized with 60 mg mL-1 sodium bismuthate. Approximately 72 % of the Am was extracted with a single contactor stage. Co-stripping of Am and Ce was demonstrated but attempts at selective stripping were not successful. Lastly, successful recycle of the used organic phase was demonstrated. Contactor efficiencies of 95-100% were obtained.
Availability note (English)
Available from https://www.osti.gov/servlets/purl/1572465; https://www.osti.gov/biblio/1572465; DOE Accepted Manuscript full text, or the publishers Best Available Version will be available free of charge after the embargo periodAdditional details
Identifiers
Publishing Information
- Journal Title
- Journal of Radioanalytical and Nuclear Chemistry
- Journal Volume
- 318
- Journal Issue
- 1
- Journal Page Range
- p. 35
- ISSN
- 0236-5731
INIS
- Country of Publication
- Hungary
- Country of Input or Organization
- United States
- INIS RN
- 53049007
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S38: RADIATION CHEMISTRY, RADIOCHEMISTRY AND NUCLEAR CHEMISTRY;
- Descriptors DEI
- 3D PRINTING; AMERICIUM 243; CERIUM 139; EXTRACTION APPARATUSES; NITRIC ACID; OXIDATION; SOLVENT EXTRACTION
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; BETA DECAY RADIOISOTOPES; CERIUM ISOTOPES; CHEMICAL REACTIONS; COMPUTER-AIDED FABRICATION; DAYS LIVING RADIOISOTOPES; ELECTRON CAPTURE RADIOISOTOPES; EQUIPMENT; EVEN-ODD NUCLEI; EXTRACTION; FABRICATION; HEAVY NUCLEI; HYDROGEN COMPOUNDS; INORGANIC ACIDS; INORGANIC COMPOUNDS; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; NITROGEN COMPOUNDS; NUCLEI; ODD-EVEN NUCLEI; OXYGEN COMPOUNDS; RADIOISOTOPES; RARE EARTH NUCLEI; SECONDS LIVING RADIOISOTOPES; SEPARATION EQUIPMENT; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTOPES; YEARS LIVING RADIOISOTOPES
Optional Information
- Contract/Grant/Project number
- AC07-05ID14517
- Funding organization
- USDOE Office of Nuclear Energy - NE (United States)
- Secondary number(s)
- INL/JOU--18-44740-Rev000; INL-CON--18-50163-Rev000; OSTIID--1572465