“…Ewing and Haaker, 1979;Byers et al, 1985;Lutze et al, 1985). To model the long-term behaviour and stability of this radioactive waste confinement host studies have concentrated on laboratory corroded basaltic and synthetic borosilicate glasses and naturally altered basaltic glasses (Furnes, 1975(Furnes, , 1978Seyfried Jr. and Bischoff, 1979;Allen, 1982;Malow et al, 1984;Crovisier et al, 1983Crovisier et al, , 1985Crovisier et al, , 1987Crovisier et al, , 1989aCrovisier et al, , 1989bGrambow, 1985;Grambow et al, 1985;Berger et al, 1987Berger et al, , 1988Berger et al, , 1994Gislason and Eugster, 1987a;Eggleton et al, 1987;Guy and Schott, 1989;Murukami et al, 1989;Jercinovic et al, 1990aJercinovic et al, , 1990bAdvocat et al, 1990Advocat et al, , 1991Advocat et al, , 1998Nesbitt and Wilson, 1992;Ghiara et al, 1993;Gislason et al, 1993;Morgenstein and Shettel, 1994;Daux et al, 1994Daux et al, , 1997Leturcq et al, 1999;Abraitis et al, 2000;Techer et al, 2001). Most of the natural glass dissolution studies were performed in either high ionic strength/seawater solutions or at high temperatures, and many were carried out in closed system batch reactors.…”