page_title: Advanced reprocessing of spent nuclear fuel
section_title: Overview of European experience in nuclear partitioning
hierarchical_section_title: Advanced reprocessing of spent nuclear fuel / Partitioning & Transmutation strategy / Overview of European experience in nuclear partitioning
caption_attribution_description: English: Schematic representation of solvent extraction and countercurrent stagewise process
context_page_description: The advanced reprocessing of spent nuclear fuel is a potential key to achieve a sustainable nuclear fuel cycle and to tackle the heavy burden of nuclear waste management. In particular, the development of such advanced reprocessing systems may save natural resources, reduce waste inventory and enhance the public acceptance of nuclear energy. This strategy relies on the recycling of major actinides and the transmutation of minor actinides. In order to fulfill this objective, selective extracting agents need to be designed and developed by investigating their complexation mechanism.
context_section_description: A lot of research funded by the European Commission is being devoted to hydrometallurgical processes for the partitioning and transmutation of trivalent actinides (An). These research programs have first led to multicycle processes, secondly to the development of simplified and innovative processes. The hydrometallurgical partitioning consists of two relevant steps: extraction and stripping. In the first step the organic phase, containing the extracting ligand dissolved in a suitable solvent, is contacted with the aqueous phase coming from the dissolution of the irradiated fuel. The solutes present in the aqueous phase are extracted by a complexation reaction with the extracting agent and transferred into the organic phase in which the formed complexes are soluble. The second step, known as stripping, is obtained by reversing the complexation reaction, where the solutes are back-extracted into another aqueous solution usually different in acidity compared to the previous one. The main goal is to develop reliable and affordable industrial separation processes by lipophilic and hydrophilic ligands to selectively extract minor actinides from the (3–4) M acidic target waste downstream of the PUREX process, but with the more challenging goal to minimize the amount of solid secondary waste. The CHON principle was born to meet this further process requirement, according to which all extractants and molecular reagents used in the developed processes have only to contain atoms of carbon (C), hydrogen (H), oxygen (O) and nitrogen (N), thus incinerable waste to easily release into the environment.
   The industrial separation processes will be implemented stepwise by annular centrifugal contactors, developed for the first time at Argonne National Laboratory in the 1970s. The countercurrent process consists of the aqueous and organic phases moving continuously in opposite directions stage by stage. The two immiscible liquids enter each contactor unit, first contacted in the annular region between the housing and the spinning rotor and then centrifuged in the inner part of the unit. Two main ways are currently followed within the partitioning strategy: the heterogeneous and homogeneous recycling. All the first European research projects on hydrometallurgical partitioning started within the heterogeneous recycling, since none of the developed extracting agents were able to selectively extract actinides directly downstream of the PUREX process. This led research to develop first multi-stage and multi-cycle processes. A two-cycle process (DIAMide EXtraction + Selective ActiNide EXtraction) was developed for a selective actinide extraction downstream of a first co-extraction (DIAMEX) of actinides and lanthanides. The recent joint research projects point to develop innovative processes with a reduced number of cycles to directly extract minor actinides (americium and curium) from the PUREX raffinate in one cycle, either by a lipophilic extractant (1cycle-SANEX) or by a hydrophilic ligand (innovative-SANEX). Recent research efforts are being devoted to the homogeneous recycling by Grouped Actinides Extraction (GANEX), which consists in a previous uranium recovery (GANEX 1) and a successive group separation of plutonium, neptunium, americium and curium actinide ions (GANEX 2).
caption: Schematic representation of solvent extraction and countercurrent stagewise process
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