PyTri-Diol behavior at conditions relevant for i-SANEX and EURO GANEX processes
- 1. Department of Energy, Politecnico di Milano, Piazza L. da Vinci 32, 20133 Milan, (Italy)
- 2. CEA, DEN, DMRC, Univ. Montpellier, LILA, Marcoule, (France)
Description
The Partitioning and Transmutation of long-term radiotoxic Transuranium elements (TRU) is a valid approach for minimizing the high-level waste and optimizing both natural resources exploitation and final repository environmental footprint. Among several processes developed so far, the i-SANEX (innovative-Selective Actinide Extraction) and EURO-GANEX (European-Grouped Actinide Extraction) concepts target the selective separation of Minor Actinides (MA: Am and Cm) or, more ambitiously, of all TRU from lanthanides (Ln) and fission products. The well-established Tetraoctyl-diglycolamide (TODGA) ligand is typically employed to co-extract Ln and MA from the aqueous feed, in association with Dimethyl-Dioctyl-hexyl-ethoxy-malonamide (DMDOHEMA) if all TRU need to be extracted. Afterwards, a hydrophilic complexing agent is required to achieve the selective actinide separation. To this aim, among several molecules proposed so far, the CHON PyTri-Diol ligand exhibited promising TRU extraction selectivity and efficiency, and unprecedented radiolytic and hydrolytic stability. In view of possible future industrial implementation, PyTri-Diol behavior has been studied in conditions closer to the process ones. The effect of temperature on PyTri-Diol extraction capability has been investigated by means of solvent extraction experiments in the temperature range of interest, namely between 10 and 50 C. Even if the MA/Eu separation factor decreases at increasing temperature, the system remains sufficiently selective for MA. Furthermore, the effects of Am and Pu loading on PyTri-Diol performances have been studied. In order to demonstrate the applicability to i-SANEX and EUROGANEX processes respectively, solvent extraction experiments were performed with synthetic aqueous feeds containing real-waste concentration of 241Am(III) and 239Pu(IV). The tests were performed with fresh, aged (1 month) and irradiated (up to 200 kGy with 2.5 kGy/h 60Co source) PyTri-Diol solutions, in some cases containing Acetohydroxamic Acid (AHA) to enhance Pu(IV) back-extraction. Remarkably, whether fresh, aged or irradiated, PyTri-Diol alone efficiently and selectively recovers Am(III) and, synergistically with AHA, Pu(IV) present in macro-concentrations. These results are very encouraging and furtherly support the implementation of i-SANEX and EUROGANEX processes based on PyTri-Diol system. (authors)
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Additional details
Publishing Information
- Imprint Pagination
- 38 p.
- Journal Page Range
- p. 12
- Report number
- INIS-FR--24-1922
Conference
- Title
- Nuclear Fuel Cycle: A Chemistry Conference
- Acronym
- NFC3 2021
- Dates
- 4-5 May 2021
- Place
- Montpellier (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 56003245
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; AMERICIUM 241; CURIUM; DIAMEX PROCESS; FISSION PRODUCTS; HIGH-LEVEL RADIOACTIVE WASTES; IMPLEMENTATION; LIGANDS; PLUTONIUM; RADIOACTIVE WASTE PROCESSING; RARE EARTHS; SOLVENT EXTRACTION; SOLVENTS; TRANSMUTATION
- Descriptors DEC
- ACTINIDE NUCLEI; ACTINIDES; ALPHA DECAY RADIOISOTOPES; AMERICIUM ISOTOPES; ELEMENTS; EXTRACTION; HEAVY NUCLEI; ISOTOPES; MANAGEMENT; MATERIALS; METALS; NUCLEI; ODD-EVEN NUCLEI; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTES; RADIOISOTOPES; REPROCESSING; SEPARATION PROCESSES; SPONTANEOUS FISSION RADIOISOTOPES; TRANSPLUTONIUM ELEMENTS; TRANSURANIUM ELEMENTS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- 2 refs.