Published 1984
| Version v1
Book
Vitrification experience and projects in France
Description
Research on the vitrification of concentrated fission product solutions has been conducted in France for over a quarter of a century. This work has resulted in the formulation of a series of borosilicate glasses applicable to the high-level wastes produced at the Marcoule and La Hague reprocessing plants. The properties of these nuclear glasses permit interim storage and future long-term disposal under safe conditions. A continuous vitrification process has also been developed and implemented on an industrial scale at Marcoule since 1978; a larger facility will begin operation at La Hague in late 1986
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- Imprint Title
- Fuel reprocessing and waste management. Volume 1
- Journal Page Range
- p. 92-100.
Conference
- Title
- ANS International topical meeting on fuel reprocessing and waste management.
- Dates
- 26-29 Aug 1984.
- Place
- Jackson Hole, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17052034
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOROSILICATE GLASS; FRANCE; HIGH-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE PROCESSING; VITRIFICATION
- Descriptors DEC
- DEVELOPED COUNTRIES; EUROPE; GLASS; MANAGEMENT; MATERIALS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES