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
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Technical Report
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Sun Jul 01 00:00:00 EDT 1973
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OSTI ID:4424528
Leach rates of high activity waste from borosilicate glass
Journal Article
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Sat Mar 31 23:00:00 EST 1979
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Leach rates of high activity waste from borosilicate glass
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Sat Dec 31 23:00:00 EST 1977
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OSTI ID:5156814
Related Subjects
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
052001* -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BORON COMPOUNDS
BORON SILICATES
DISSOLUTION
EUROPE
FISSION PRODUCTS
FRANCE
GLASS
ISOTOPES
LEACHING
MANAGEMENT
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
SEPARATION PROCESSES
SILICATES
SILICON COMPOUNDS
SOLIDIFICATION
STABILITY
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING
052001* -- Nuclear Fuels-- Waste Processing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BORON COMPOUNDS
BORON SILICATES
DISSOLUTION
EUROPE
FISSION PRODUCTS
FRANCE
GLASS
ISOTOPES
LEACHING
MANAGEMENT
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTE PROCESSING
SEPARATION PROCESSES
SILICATES
SILICON COMPOUNDS
SOLIDIFICATION
STABILITY
VITRIFICATION
WASTE MANAGEMENT
WASTE PROCESSING