Published November 1984 | Version v1
Report Open

Alterability of the French LWR solution reference glass in repository conditions

  • 1. CEA, CEN Valrho, 30 - Bagnols-sur-Ceze (France)
  • 2. CEA, CEN Cadarache, 13 - Saint-Paul-lez-Durance (France)

Description

The disposal of glass blocks containing fission products in granitic geological formations is one of the options currently investigated in France. This paper discusses the major criteria selected to develop models of such repositories and gives the first results obtained with the corresponding experimental test. Five laboratory mockups corresponding to different alternatives regarding the fill materials were prepared. The following materials were used to encase the French LWR reference glass: - Test 1: granite, sand, stainless steel; Test 2: granite, sand, illite, stainless steel; - Test 3: granite, sand, bentonite, stainless steel; - Test 4: granite, sand, Al2O3, AZS, stainless steel; -test 5: granite, sand, hastelloy C4. Samples were taken of the solutions obtained in the preconditioning cell and in contact with the glass to assess the glass corrosion behavior in each of these media. The experiments were completed by surface analyses designed to compare the morphology of the surface layers that develop with and without the environmental materials

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MF available from INIS under the Report Number.

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Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
CEA-CONF--7526

Conference

Title
Symposium on the scientific basis for nuclear waste management.
Dates
26-30 Nov 1984.
Place
Boston, MA (USA).