Fabrication of (U,Am)O2 pellet with controlled porosity from oxide microspheres
Source abstract
Abstract
Abstract U 1-x Am x O 2±δ mixed-oxides are considered as promising compounds for americium heterogeneous transmutation in Sodium Fast Neutron Reactor. Porous microstructure is envisaged in order to facilitate helium and fission gas release and to reduce pellet swelling during irradiation and under self-irradiation. In this study, the porosity is created by reducing (U,Am) 3 O 8 microspheres into (U,Am)O 2 during the sintering. This reduction is accompanied by a decrease of the lattice volume that leads to the creation of open porosity. Finally, an (U 0.90 Am 0.10 )O 2 porous ceramic pellet (D∼89% of the theoretical density TD) with controlled porosity (≥8% open porosity) was obtained from mixed-oxide microspheres obtained by the Weak Acid Resin (WAR) process.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear materials and radiation effects · Radioactive element chemistry and processing
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (20)
Show source-provided references
1. 2012
2. Perspectives on the closed fuel cycle – implications for high-level waste matrices10.1016/j.jnucmat.2007.01.210 ↗
3. Status of the French research program on partitioning and transmutation10.1080/18811248.2007.9711302 ↗
4. The Generation IV Internationl Forum, (n.d.). https://www.gen-4.org/gif/ (accessed December 1, 2014).
5. Fabrication and characterisation of U0.85Am0.15O2-x discs for MARIOS irradiation program10.1016/j.jnucmat.2011.05.036 ↗
6. Application of the UMACS process to highly dense U1-xAmxO2±δ MABB fuel fabrication for the DIAMINO irradiation10.1016/j.jnucmat.2012.07.018 ↗
7. Transmutation: issues, innovative options and perspectives10.1016/S0149-1970(02)00031-8 ↗
8. Transmutation of actinides in inert-matrix fuels: fabrication studies and modelling of fuel behaviour10.1016/S0022-3115(99)00043-4 ↗
9. Fabrication and characterization of americium, neptunium and curium bearing MOX fuels obtained by powder metallurgy process10.1016/j.jnucmat.2011.10.016 ↗
10. The results of the irradiation experiment MARIOS on americium transmutation10.1016/j.anucene.2013.05.043 ↗
11. Calcined resin microsphere pelletization (CRMP): a novel process for sintered metallic oxide pellets10.1016/j.jeurceramsoc.2012.04.011 ↗
12. Nanostructured gadolinium-doped ceria microsphere synthesis from ion exchange resin: multi-scale in-situ studies of solid solution formation10.1016/j.jssc.2014.06.028 ↗
13. Étude de la synthèse de sphères d’oxyde d’actinides et/ou de lanthanides et de leur aptitude à la céramisation
14. Fabrication of uranium–americium mixed oxide pellet from microsphere precursors: application of CRMP process10.1016/j.jnucmat.2014.06.048 ↗
15. Fabrication of uranium dioxide ceramic pellets with controlled porosity from oxide microspheres10.1016/j.jnucmat.2014.01.017 ↗
16. Picart · 2012
17. P.A. Haas, 3.800.023, 1974.10.1136/bmj.3.5934.800 ↗
18. Self-irradiation effects in dense and tailored porosity U1-yAmyO2-x (y = 0.10; 0.15) compounds10.1016/j.jnucmat.2010.12.314 ↗
19. Recent progress on minor-actinide-bearing oxide fuel fabrication at CEA Marcoule10.1016/j.jnucmat.2013.02.079 ↗
20. Local structure and charge distribution in mixed uranium–americium oxides: effects of oxygen potential and Am content10.1021/ic200910f ↗