Reactive sintering of U 1-yAm yO 2±x in overstoichiometric conditions

Journal of the European Ceramic Society

Volumn 32, Issue 8, 2012, Pages 1585-1591

  Prieur, D ^a,d   Lebreton, F ^a   Martin, P M ^b   Jankowiak, A ^c   Delahaye, T ^a   Dehaudt, P ^a   Blanchart, P ^d  

^a DIF   (France)

^b IRFM   (France)

^c SRMA   (France)

^d University of Limoges   (France)

Author keywords

Americium; Nuclear applications; Sintering; UO 2; X ray methods

Indexed keywords

DIFFUSION PROCESS; FUEL FABRICATIONS; LOW DENSITY; NUCLEAR APPLICATIONS; OVER-STOICHIOMETRIC; OXYGEN POTENTIAL; REACTIVE SINTERING; SOLID SOLUTION FORMATION; UO 2; X-RAY METHODS; XAFS; XRD;

AMERICIUM; PELLETIZING;

SINTERING;

EID: 84863418506     PISSN: 09552219     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.jeurceramsoc.2011.12.017     Document Type: Article

References (20)

1. Warin D. Status of the French research program on partitioning and transmutation. Journal of Nuclear Science and Technology 2007, 44:410-414.
2. Lebreton F., Prieur D., Jankowiak A., Delahaye T., Tribet M., Donnet L., et al. Fabrication and characterization of americium, neptunium and curium bearing MOX fuels obtained by powder metallurgy process. Journal of Nuclear Materials 2011, 420:213-217.
3. 2-x for MARIOS irradiation program. Journal of Nuclear Materials 2011, 414:503-507.
4. Grouiller J.P., Pillon S., de Saint Jean C., Varaine F., Leyval L., Vambenepe G., et al. Minor actinides transmutation scenario studies with PWRs, FRs and moderated targets. Journal of Nuclear Materials 2003, 320:163-169.
5. Delpech M., Grouiller J.P. NT DER/SPRC/LEDC 1997, 96-462.
6. 2-x (y=0.1; 0.15) pellet macroscopic swelling. Advances in Science and Technology 2010, 73:104-108.
7. 2-x (y=0.10; 0.15) compounds. Journal of Nuclear Materials 2011, 411:15-19.
8. Prieur D., Martin P.M., Jankowiak A., Scheinost A., Herlet N., Dehaudt P., et al. Local structure and charge distribution in mixed uranium-americium oxides: effects of oxygen potential and Am content. Inorganic Chemistry 2011, 50:12437-12445.
9. 8 in various atmospheres. Journal of Nuclear Materials 1959, 1:28-38.
10. 2+x. Journal of Nuclear Materials 1992, 189:175-182.
11. Prieur D., Jankowiak A., Leorier C., Herlet N., Donnet L., Dehaudt P., et al. Fabrication and characterization of minor actinides bearing fuels obtained by conventional powder metallurgy process. Powder Technology 2011, 208:553-557.
12. Carjaval JR. Satellite meeting on powder diffraction of the XV IUCr Congress; 1990.
13. 2. Inorganic Chemistry 2009, 48:7585-7592.
14. Belin R.C., Martin P.M., Valenza P.J., Scheinost A.C. Experimental insight into the radiation resistance of zirconia-based americium ceramics. Inorganic Chemistry 2009, 48:5376-5381.
15. Grandjean S., Arab-Chapelet B., Robisson A.C., Abraham F., Martin Ph, Dancausse J.P., et al. Structure of mixed U(IV)-An(III) precursors synthesized by co-conversion methods (where An=Pu, Am or Cm). Journal of Nuclear Materials 2009, 385:204-207.
16. Ravel B., Newville M. ATHANE, ARTEMIS, HEPHAESTUS: data analysis for X-ray absorption spectroscopy using IFEFFIT. Journal of Synchrotron Radiation 2005, 12:537-541.
17. 2 microstructure by oxidative sintering. Journal of Nuclear Materials 1986, 140:1-6.
18. Rocaniere C. Contribution to the study of the systems uranium oxide - lanthanoide oxide. Ph.D. Thesis, University of Limoges; 1998.
19. 2-x. Journal of Nuclear Materials 2003, 320:292-298.
20. Matzke H. Point defects and transport properties in carbides. Solid State Ionics 1984, 12:25-45.