Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Vitrification of fission product solutions in France (in French)

Journal Article · · Nucl. Technol.; (United States)
OSTI ID:7089516
The current approach in France to the problem of waste management of the solutions of concentrated fission products from fuel reprocessing is solidification by vitrification. The solidification processes utilized are a batch process, in-pot vitrification, and a continuous process, a rotary kiln calciner. Generally, a silicate glass that is more stable than the phosphate is used. The problem of separation of a molybdate phase at high fission product concentration is reduced by an increase in B/sub 2/O/sub 3/ concentration. For wastes from a U-Mo fuel that contains 100 g/l of molybdenum, phase separation is reduced by addition of Al/sub 2/O/sub 3/. Leach rates for the borosilicate glass were studied, and rates of 10/sup -8/ to 10/sup -6/ g/cm/sup 2/ per day were measured as a function of Na/sub 2/O concentration. Plutonium leach rates were measured as a function of Na/sub 2/O concentration. Plutonium leach rates were measured as 10/sup -8/ to 10/sup -7/ g/cm/sup 2/ per day and /sup 241/Am was 8 x 10/sup -9/ g/cm/sup 2/ per day after 110 days of leaching. Stability of the glasses to alpha-particle radiation damage was simulated for a storage period of 10 to 1000 yr. These samples indicated only a slight change in viscosity as a result of these simulation studies.
Research Organization:
Commissariat a l'Energie Atomique de Marcolue Service des Ateliers-Pilotes, France
OSTI ID:
7089516
Journal Information:
Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 34:3; ISSN NUTYB
Country of Publication:
United States
Language:
French