Hydrotalcite formed by alteration of R7T7 nuclear waste glass and basaltic glass in salt brine at 190{degrees}C

Conference · Sat Dec 31 00:00:00 EST 1994

OSTI ID:47895

Abdelouas, A; Crovisier, J L ^[1]; Lutze, W; Mueller, R; Bernotat, W ^[2]

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1. Centre de Geochimie de la Surface, Strasbourg (France)
2. Kernforschungszentrum Karlsruhe (Germany)

The R7T7 and synthetic basaltic glasses were submitted to corrosion in a saline MgCl{sub 2} dominated solution at 190{degrees}C. For both glasses, the early alteration product is a hydrotalcite-like compound in which HPO{sub 4}{sup 2{minus}}, SO{sub 4}{sup 2{minus}} and Cl{sup {minus}} substitutes to CO{sub 3}{sup 2{minus}}. The measured d{sub 003} spacing is 7.68 {angstrom} for the hydrotalcite formed from R7T7 glass and 7.62 {angstrom} for the hydrotalcite formed from basaltic glass which reflect the high aluminium content. Chemical microanalyses show that the hydrotalcite is subsequently covered by a silica-rich gel which evolves into saponite after few months.

• OSTI ID: 47895
• Report Number(s): CONF-931108-Vol.333; TRN: 95:011401
• Resource Relation: Conference: Fall meeting of the Materials Research Society (MRS), Boston, MA (United States), 29 Nov - 3 Dec 1993; Other Information: PBD: 1994; Related Information: Is Part Of Scientific basis for nuclear waste management XVII; Barkatt, A. [ed.] [Catholic Univ. of America, Washington, DC (United States)]; Van Konynenburg, R.A. [ed.] [Lawrence Livermore National Lab., CA (United States)]; PB: 964 p.
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
BOROSILICATE GLASS
CORROSION
PHASE STUDIES
HIGH-LEVEL RADIOACTIVE WASTES
RADIOACTIVE WASTE PROCESSING
UNDERGROUND STORAGE
VITRIFICATION
SALT DEPOSITS
RADIOACTIVE WASTE DISPOSAL
GORLEBEN SALT DOME
UNDERGROUND FACILITIES
BASALT