#	Pagina
attuale pagina	/open-h2020/projects/210831/results.html

Report

Teaser, summary, work performed and final results

Periodic Reporting for period 1 - GENIORS (GEN IV Integrated Oxide fuels recycling strategies)

Teaser

Summary

The current open nuclear fuel cycle utilises only approximately one percent of the energy contained in natural uranium. Spent fuel recycling (as done e. g. in France) results in significantly increased fuel efficiency. Future multi-recycling strategies to be deployed in fast reactors will lead to further improvement, eventually rendering further uranium mining unnecessary, if depleted uranium stockpile is available.
In this context and in the continuity of previous EURATOM projects (NEWPART, PARTNEW, EUROPART, ACSEPT, SACSESS), GENIORS addresses research and innovation in fuel cycle chemistry and physics. More specifically, GENIORS carries out research and innovation for developing compatible techniques for dissolution, reprocessing and manufacturing of innovative oxide fuels, potentially containing minor actinides, in a â€œfuel to fuelâ€ approach, taking into account safety issues under normal and mal-operation. The most promising options developed in prior EURATOM projects are further developed to address the challenges specific to GEN IV. To deliver the full picture of a MOX fuel cycle, GENIORS works in close collaboration with the INSPYRE project on oxide fuels performance.
By implementing a three-step approach (reinforcement of the scientific knowledge â€” process development and testing â€” system studies, safety and integration), GENIORS contributes to the provision of more science-based strategies for nuclear fuel management in the EU. It will support nuclear energy to contribute significantly and sustainably to EU energy independence. In the longer term, it will facilitate the management of ultimate radioactive waste by reducing its volume and radiotoxicity.

Work performed

WP1 Fission product behaviour aims at investigating the solution and extraction chemistry of key fission products. It includes the extraction chemistry of key fission products and their speciation in aqueous and organic solutions.
WP2 Degradation chemistry aims at ensuring a safe long-term performance of a chemical system submitted to radiation. Based on background from previous projects about the stability of DGA and BTBPs, studies carried out have deepened in the stability of the molecules, loses of efficiency, the behaviour and impact of troublesome degradation products, risks, and possible mal operation situation.
WP3 Solvent extraction chemistry aims at improving the understanding and optimization of the chemical systems developed for solvent extraction separation processes. The 1st task focuses on the fundamental understanding of the chemistry involved in these processes. The last three tasks focus on processes developments, with an integrated approach taking into account the modelling, loading capacities, and clean-up of the extraction systems.
WP4 Solid/liquid interface chemistry aims at better understanding the phenomena occurring at the solid/liquid interfaces during reprocessing of spent nuclear fuel. The 1st task is devoted to the understanding of the solid/liquid interface during dissolution tests performed on actinide bearing dioxide compounds. The 2nd task focuses on the conversion of actinides from solution by precipitation of original precursors coming from new chemical processes based on wet chemistry routes. The goal is to prepare designed precursors of actinide dioxide based materials in terms of chemical composition, morphology, microstructure and physico-chemical properties.
WP5 Process & Flowsheet modelling & safety: several crucial parameters have been identified for relevant modelling and estimations of safety and operation. Process optimisation with focus on sensitivity studies and solvent degradation has been performed as well as relevant loading conditions of such elements as plutonium.
WP6 Process Optimisation & testing: the baseline processes for homogeneous recycling (EURO-GANEX) and heterogeneous recycling (i-SANEX) of minor actinides will be optimised. Key objectives are related to increasing the feed envelope, improving decontamination of products from fission products, simplifying the process and replacing sulphur-containing aqueous ligands with CHON ligands that are easily decomposed.
WP7 Dissolution, Conversion & interface with SX: Nitric dissolution of mixed uranium plutonium oxide may be difficult depending on Pu content and/or morphology of the oxides. Dissolution of single phases UxPu1-xO2Â± exhibiting different Pu content and/or morphologies are being carried out to allow establishment of dissolution models describing both morphology and Pu content effects. Determination of solubility modification is being studied and curative option to get rid of organic residues using mediated electrochemical oxidation is tested. Safer minor actinide enriched oxide synthesis routes are being tested to produce minor actinide bearing blanket with less dust dissemination increasing safety.
WP8 System studies aims at delivering an assessment of the holistic effects of chemistry changes in the nuclear fuel cycle. The main results include a concept design of a Euro-Ganex reprocessing plant, a study comparing different options for solvent extraction, a mapping of different partitioning and transmutation strategies, spent fuel recycling scenarios and a simulation model to illustrate changes in reprocessing plants.
WP10 Fuel cycle integration: a stakeholder svent was organized on 24/10/2018 and a clustering event on 25/10/2018. They intended to provide insight on the current state of the art of partitioning and transmutation and to put this in the context of the nuclear fuel back-end scenarios currently implemented or intended to be implemented in the EU countries and beyond. Active contribution was obtained

Final results

In accordance with SNETP strategic agenda and more specifically with ESNII, GENIORS focuses on GEN IV systems based on oxide fuel and requiring a multi recycling of this fuel, with or without minor actinides. GENIORS will work in close collaboration with the INSPYRE project on oxide fuels performance.
To be sure that the right level of information, including the most recent developments, is available, GENIORS will also work in close collaboration with other projects dealing with fuel, materials and waste management, in order to identify as soon as possible potential issues to be addressed or R&D gaps to be filled on the separation chemistry side to ensure the relevance of the developed strategies. GENIORS relies on a strong technical background that will be exploited and developed further.