The FUTURIX-FTA experiment in Phenix: status of oxides fuels fabrication
- Commissariat a l'Energie Atomique (CEA), CEA/DEN/VRH/DTEC, BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)
- Commissariat a l'Energie Atomique (CEA), CEA/DEN/VRH/DRCP, BP 17171, 30207 Bagnols-sur-Ceze Cedex (France)
Eliminating long-lived radionuclides by transmuting them into nonradioactive or short-lived nuclei is a reference approach in nuclear waste management. FUTURIX/FTA (FUels for Transmutation of transuranium elements in Phenix / Fortes Teneurs en Actinides [high actinide content]) is an international program intended to demonstrate the technical feasibility, primarily with regard to fuel behavior, of transmuting minor actinides in fast neutron reactors. This research is carried out in collaboration with the US Department of Energy (DOE), the Japan Atomic Energy Research Institute (JAERI), the Institute for Transuranium Elements (ITU) in Germany, and the Commissariat a l'Energie Atomique (CEA) in France. In this context, the CEA investigated four ceramic/ceramic (cercer) compositions ((Pu{sub 0.5}Am{sub 0.5})O{sub 2-x} + 80 vol% MgO), (Pu{sub 0.5}Am{sub 0.5})O{sub 2-x} + 70 vol% MgO), (Pu{sub 0.2}Am{sub 0.8})O{sub 2-x} + 75 vol% MgO), (Pu{sub 0.2}Am{sub 0.8})O{sub 2-x} + 65 vol% MgO) and fabricated two fuel pins. The mixed actinide oxides were synthesized by oxalate co-conversion and incorporated into a magnesia matrix by classical powder metallurgy. The resulting fuel pellets were subjected to chemical, dimensional, structural and microstructural characterization. The results for each composition were interpreted and compared. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 20979704
- Resource Relation:
- Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 11 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
- Country of Publication:
- United States
- Language:
- English
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