Determination of the Forward Dissolution Rate for International Simple Glass in Alkaline Solutions

The International Simple Glass (ISG) is considered as reference benchmark glass and is used in the frame of an international collaboration for the study of the dissolution mechanisms of high-level vitrified nuclear waste. In this work the forward dissolution rate of the ISG was determined in different alkaline solutions, as a simulation of the disposal conditions foreseen by the Belgian concept for geological disposal of vitrified waste. The determination of the forward dissolution rate was done by measuring the Si released from the glass in solution in tests performed at 30 °C in four different KOH solutions with pH varying from 9 to 14 and in artificial cementitious water at pH 13.5. The forward dissolution rates determined for the ISG in high pH solutions are in good agreement with the results obtained for a lower pH range. The rates obtained in this study, moreover, were compared with the rates measured in the same conditions for SON68 glass from a previous work. The values obtained for the two glasses are comparable in artificial cementitious water and in KOH at moderately alkaline pH. At higher pH, ISG glass shows a lower forward dissolution rate with respect to SON68 (0.20 g•m^−2•d for ISG and 0.35 g•m^−2 d for SON68 at pH 14).

[1]  K. Lemmens,et al.  Transport- and surface reaction-controlled SON68 glass dissolution at 30 °C and 70 °C and pH = 13.7 , 2015 .

[2]  S. Gin,et al.  The fate of silicon during glass corrosion under alkaline conditions: A mechanistic and kinetic study with the International Simple Glass , 2015 .

[3]  P. Frugier,et al.  Resumption of Alteration at High Temperature and pH: Rates Measurements and Comparison with Initial Rates , 2014 .

[4]  A. Abdelouas,et al.  A Preliminary Investigation of the ISG Glass Vapor Hydration , 2013 .

[5]  K. Idemitsu,et al.  Initial Dissolution Rate of the International Simple Glass as a Function of pH and Temperature Measured Using Microchannel Flow‐Through Test Method , 2013 .

[6]  N. Hyatt,et al.  Dissolution of UK high-level waste glass under simulated hyperalkaline conditions of a colocated geological disposal facility , 2013 .

[7]  N. Hyatt,et al.  Formation of alteration products during dissolution of vitrified ILW in a high-pH calcium-rich solution , 2013 .

[8]  S. Gin,et al.  Antagonist effects of calcium on borosilicate glass alteration , 2013 .

[9]  K. Mueller,et al.  An international initiative on long-term behavior of high-level nuclear waste glass , 2013 .

[10]  N. Hyatt,et al.  Dissolution of vitrified wastes in a high-pH calcium-rich solution , 2013 .

[11]  N. Hyatt,et al.  Chemical durability of vitrified wasteforms: effects of pH and solution composition , 2012, Mineralogical Magazine.

[12]  M. I. Ojovan,et al.  Glassy Wasteforms for Nuclear Waste Immobilization , 2011 .

[13]  Jean-Eric Lartigue,et al.  SON68 nuclear glass dissolution kinetics: Current state of knowledge and basis of the new GRAAL model , 2008 .

[14]  K. Lemmens,et al.  Determination of the Forward Rate of Dissolution for SON68 and PAMELA Glasses in Contact With Alkaline Solutions , 2008 .

[15]  Seung-Young Jeong,et al.  Effects of Iron and pH on Glass Dissolution Rate , 2002 .

[16]  B. Grambow.  Source Trends for Performance Assessment of HLW Glass and Spent Fuel as Waste Forms , 1997 .

[17]  T. Advocat,et al.  Hydrolysis of R7T7 Nuclear Waste Glass in Dilute Media: Mechanisms and Rate as a function of Ph , 1990 .

[18]  D. K. Smith,et al.  Dissolution Kinetics of a Simple Analogue Nuclear Waste Glass as a Function of Ph, Time and Temperature , 1989 .

[19]  P. L. Buldini,et al.  Rapid determination of dissolved silica in natural waters , 1985 .