HLW vitrification in France industrial experience and glass quality
For the HLW issued from the reprocessing of LWR fuels, research and development in high level waste vitrification in France have been carried out for 30 years. Today, the commercial service is now on line at the La Hague plant in R7 and T7 facilities. Long term studies performed by the CEA (French Atomic Energy Commission) resulted in the formulation of so-called R7 and T7 glass whose main components have been specified. The vitrified waste specifications were subjected to peer review by an independent commission of scientists and nuclear experts. They were also provided to ANDRA, the national waste management agency, for comment before submittal to DSIN, the nuclear regulatory authority of France, for approval. The DSIN approved the glass waste form for disposal in February 1986. Subsequently, the R7/T7 glass specifications were approved by the regulatories authorizes of Cogema`s reprocessing clients in Belgium, Germany, Netherlands, Switzerland and Japan. The quality of the vitrified glass produced and canisters compliance with agreed specifications are demonstrated through characterization studies. Since the active start-up of R7/77 facilities, canisters compliance with specifications relies upon a complete quality assurance/quality control programme including process control.
- OSTI ID:
- 182122
- Report Number(s):
- CONF-940501-; ISSN 0003-018X; TRN: 96:006840
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 70, Issue Suppl.1; Conference: 9. Pacific basin nuclear conference, Sydney (Australia), 1-5 May 1994; Other Information: PBD: 1994
- Country of Publication:
- United States
- Language:
- English
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