In November/December 2004, AREVA succeeded in reprocessing for the first time MOX spent fuels with a continuous dissolution process on the UP2-800 plant in La Hague. It was the industrial conclusion of preliminary and extensive studies realized by the CEA teams at the laboratory scale in Atalante facilities. The experiments were realized using MOx fuel obtained by MIMAS process and irradiated in Saint-Laurent des Eaux power reactor. The average burn-ups of the pin samples used for the studies were comprised between 28 GWd/T and 43 GWd/T. As the MOx fuel present a specific behavior versus dissolution due to the presence of PuO2 clusters, the solubility tests were mainly focused on the Pu behavior as a function of the temperature of dissolution (from 88 °C to boiling point) and the fuel burn-up. The fixed dissolution parameters were the residence time (8 hours), the initial acidity (near 8 M) and the sample size (35 mm). Available results concern dissolution kinetics, plutonium solubility and its distribution in the different flux (insoluble solids, solution).
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16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4815-9
PROCEEDINGS PAPER
CEA Preliminary Studies for Industrial MOx Reprocessing: From Laboratory Results to Successful First Industrial Campaign on UP2-800 Areva Plant
N. Reynier Tronche,
N. Reynier Tronche
CEA Atalante, Bagnols sur Ce`ze, France
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C. Eysseric,
C. Eysseric
CEA Atalante, Bagnols sur Ce`ze, France
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JP. Dancausse
JP. Dancausse
CEA Atalante, Bagnols sur Ce`ze, France
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N. Reynier Tronche
CEA Atalante, Bagnols sur Ce`ze, France
C. Eysseric
CEA Atalante, Bagnols sur Ce`ze, France
JP. Dancausse
CEA Atalante, Bagnols sur Ce`ze, France
Paper No:
ICONE16-48198, pp. 51-54; 4 pages
Published Online:
June 24, 2009
Citation
Reynier Tronche, N, Eysseric, C, & Dancausse, J. "CEA Preliminary Studies for Industrial MOx Reprocessing: From Laboratory Results to Successful First Industrial Campaign on UP2-800 Areva Plant." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 2: Fuel Cycle and High Level Waste Management; Computational Fluid Dynamics, Neutronics Methods and Coupled Codes; Student Paper Competition. Orlando, Florida, USA. May 11–15, 2008. pp. 51-54. ASME. https://doi.org/10.1115/ICONE16-48198
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