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French Industrial Vitrification Plant: 30 Years Old and Still Innovating

Published online by Cambridge University Press:  15 February 2011

E. Chauvin
Affiliation:
AREVA NC, 1 Place Jean Millier, 92084 Paris La Defense, France
C. Ladirat
Affiliation:
CEA, Valhro, BP 171, Batiment 208, 30207 Bagnols sur Ceze Cedex, France
R. Do Quang
Affiliation:
AREVA NC, 1 Place Jean Millier, 92084 Paris La Defense, France
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Abstract

In 2008, AREVA NC Industrial Vitrification of High-Level Liquid Waste blows out its 30th candle, with always two main objectives during all the time: containment of the long lived fission products and reduction of the final volume of waste. During all this time AREVA with the French Atomic Energy Commission (CEA) developed and use in their industrial installations a selection of borosilicate glass that have been demonstrated as the most suitable containment matrix for waste from spent nuclear fuel. Consistent and long-term R&D programs associated to industrial feed back from operation have enabled continuous improvement of the process: throughput and waste loading factor enhancement. The Vitrification Process used and currently implemented in the AREVA facilities will be described.

Type
Research Article
Copyright
Copyright © Materials Research Society 2009

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References

1 Quang, R. Do, Desvaux, JL., Mougnard, P., Jouan, A., Ladirat, C., “COGEMA experience in operating and dismantling HLW melter”, ACERS, St Louis (2002).Google Scholar
2 Cheron, P., Chevalier, P., Quang, R. Do, Senoo, M., Banba, T., Fillet, C., Jacquetfrancillon, N. and al, “Examination and characterization of an active glass sample produced by COGEMA”, MRS proceedings, Vol.353 (1995)Google Scholar
3 Petitjean, V., Fillet, C., Boen, R., Veyer, C., Flament, T., “Development of Vitrification process and glass formulation for nuclear waste conditioning”, Waste Management, Tucson (2002)Google Scholar
4 Ledoux, A., Lacombe, J., Pinet, O, Dussossoy, J.L., Grandjean, A., Gruber, P., Pruvost, G., Tronche, E., Ladirat, C., Chauvin, E., Quang, R. Do, Naline, S., “Methodology of Qualification of CCIM Vitrification Process Applied to the Decontamination Effluent of the La Hague UP2-400 facility”, Waste Management, Phoenix (2009)Google Scholar