Published 1994 | Version v1
Report Open

Vitrification in La Hague plant achievement

  • 1. CEA Centre d'Etudes de la Vallee du Rhone, 30 - Marcoule (France). Dept. des Procedes de Retraitement
  • 2. Compagnie Generale des Matieres Nucleaires (COGEMA), 78 - Velizy-Villacoublay (France)
  • 3. Societe Generale pour les Techniques Nouvelles (SGN), 78 - Saint-Quentin-en-Yvelines (France)

Description

Research and development at the CEA (the French Atomic Energy Commission) about vitrification process of radioactive wastes have focused on two main points: the glass formulation to obtain the best physical, thermal and mechanical properties for the best homogeneity, stability and resistance to radiations and leaches, and the industrial process to obtain the best flexibility for the production of different homogeneous glasses and for the minimization of technological wastes. This has led to the establishment of glass specifications, agreed by the French authorities, independent commission of nuclear experts, and foreign customers, and to the construction of the R7 and T7 industrial facilities at La Hague (France) which started-up in 1989 and 1992, respectively. A description of the process units and of the quality controls are given. Various improvements have been achieved and have demonstrated the industrial mastery of vitrification of fission products. The process has proven to be flexible since fine particles from the dissolution step and alkaline effluents from the solvent regeneration steps have been incorporated to the glass matrix. (J.S.). 1 fig., 2 tabs

Availability note (English)

MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
6 p.
Report number
CEA-CONF--12175

Conference

Title
4. International Conference on Nuclear Fuel Reprocessing and Waste Management.
Dates
24-28 Apr 1994.
Place
London (United Kingdom).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
27048521
Subject category
S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S42: ENGINEERING; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACTINIDES; AIR FILTERS; CALCINATION; CALCINED WASTES; CEA LA HAGUE; CEA MARCOULE; CESIUM 137; CONTAINERS; CONTAINMENT SYSTEMS; COOLING SYSTEMS; DECONTAMINATION; EXTRACTION COLUMNS; FISSION PRODUCTS; FRANCE; LICENSING PROCEDURES; LICENSING REGULATIONS; LIQUID WASTES; PERSONNEL DOSIMETRY; RADIATION MONITORING; RADIATION PROTECTION; RADIOACTIVE WASTE MANAGEMENT; RADIOACTIVE WASTE PROCESSING; RADIOLYSIS; REPROCESSING; SAFETY REPORTS; STRONTIUM 90; SURFACE CONTAMINATION; WASTE PROCESSING PLANTS
Descriptors DEC
ADMINISTRATIVE PROCEDURES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CEA; CESIUM ISOTOPES; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CLEANING; CONTAINMENT; CONTAMINATION; DECOMPOSITION; DEVELOPED COUNTRIES; DOSIMETRY; ELEMENTS; ENGINEERED SAFETY SYSTEMS; EQUIPMENT; EUROPE; EVEN-EVEN NUCLEI; EXTRACTION APPARATUSES; FILTERS; FRENCH ORGANIZATIONS; FUEL REPROCESSING PLANTS; INDUSTRIAL PLANTS; INTERMEDIATE MASS NUCLEI; ISOTOPES; LAWS; MANAGEMENT; MATERIALS; METALS; MONITORING; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUCLEI; ODD-EVEN NUCLEI; POLLUTION CONTROL EQUIPMENT; PYROLYSIS; RADIATION EFFECTS; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; RADIOISOTOPES; REGULATIONS; SEPARATION EQUIPMENT; SEPARATION PROCESSES; STRONTIUM ISOTOPES; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WESTERN EUROPE; YEARS LIVING RADIOISOTOPES