Published 1984 | Version v1
Book

Vitrification experience and projects in France

Creators

  • 1. Commissariat a L'Energie Atomique

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