Alterability of the French LWR solution reference glass in repository conditions
Creators
- 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
Availability note (English)
MF available from INIS under the Report Number.Files
16049727.pdf
Files
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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).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 16049727
- Subject category
- S36: MATERIALS SCIENCE; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOROSILICATE GLASS; CONTAINERS; CORROSION; GRANITES; GROUND WATER; LEACHATES; LEACHING; MEDIUM PRESSURE; MEDIUM TEMPERATURE; MOCKUP; PH VALUE; RADIOACTIVE WASTE STORAGE; UNDERGROUND STORAGE
- Descriptors DEC
- CHEMICAL REACTIONS; DISPERSIONS; DISSOLUTION; GLASS; HOMOGENEOUS MIXTURES; HYDROGEN COMPOUNDS; IGNEOUS ROCKS; MANAGEMENT; MIXTURES; OXYGEN COMPOUNDS; ROCKS; SEPARATION PROCESSES; SOLUTIONS; STORAGE; STRUCTURAL MODELS; WASTE MANAGEMENT; WASTE STORAGE; WATER