Effect of Fe2O3/ZnO on Two Glass Compositions for Solidification of Swedish Nuclear Wastes

1981 ◽  
Vol 11 ◽  
Author(s):  
J. L. Nogues ◽  
L. L. Hench
Keyword(s):  
Nuclear Waste ◽  
Glass Surface ◽  
Fission Products ◽  
Waste Glass ◽  
Nuclear Wastes ◽  
Leaching Behavior ◽  
Waste Products ◽  
Simulated Waste ◽  
Nuclear Waste Glass ◽  
Glass Compositions

A recent study concluded that addition of Fe203 to a soda borosilicate nuclear waste glass may significantly reduce damage by water attack due to formation of a Fe-rich film on the glass surface. However, differences in SiO2, B203, CaO, and concentration of fission products in previous glass compositions make it impossible to ascribe the improved leach resistance solely to Fe203 content. In the present work, leaching behavior of two glasses are compared which differ only by the substitution of Fe203 for some of the ZnO in the glass. Both glass compositions, Table 1, are compatible with the French AVM process and contain 9% (by weight) of simulated waste products characteristic of the Swedish nulcear waste program.

Burial Effects on Nuclear Waste Glass

1981 ◽  
Vol 11 ◽  
Author(s):  
Larry L. Hench ◽  
Lars Werme ◽  
Alexander Lodding
Keyword(s):  
Ambient Temperature ◽  
Nuclear Waste ◽  
Storage System ◽  
Fission Products ◽  
Waste Glass ◽  
Nuclear Waste Storage ◽  
Waste Storage ◽  
Nuclear Waste Glass ◽  
Deep Boreholes ◽  
Glass Compositions

The purpose of this experiment was to evaluate the effects of various components of the SKBF/KBS nuclear waste storage system on the leaching of the vitreous waste form. Two cohfigurations of nuclear waste glasses, canisters, overpacks, and backfill mate-7ial were inserted into 5.6 cm x 3 m deep boreholes located at the 350 m level in the STRIPA mine. Some were maintained at 90°C. The others were allowed to equilibrate at the ambient temperature of the mine, approximately 8°C. Two borosilicate nuclear waste glass compositions (termed ABS 39 and ABS 41) compatible with the French AVM process containing 9 percent by weight of simulated fission products were compared. The two compositions ( Table 1) bracket the range of Si02/Na2O/B203 ratios likely to be selected for commercial vitrification operations at La Hague.

The Effect of Various Lead Species on the Leaching Behavior of Borosilicate Waste Glass

1984 ◽  
Vol 44 ◽  
Author(s):  
Richard L. lehman ◽  
Frank A. Kuchinski
Keyword(s):  
Weight Loss ◽  
Glass Surface ◽  
Lead Concentration ◽  
Pure Water ◽  
Waste Glass ◽  
Leaching Behavior ◽  
Weight Loss Data ◽  
Nuclear Waste Glass ◽  
Lead Metal ◽  
Lead Species

AbstractA borosilicate nuclear waste glass was static leached in pure water, silicate water, and brine solution. Three different forms of lead were included in specified corrosion cells to assess the extent to which various lead species alter the leaching behavior of the glass. Weight loss data indicated that Pbm and Pb0 greatly reduce the weight loss of glass when leached in pure water, and similar effects were noted in silicate and brine. Si concentrations, which were substantial in the glass-alone leachate, were reduced to below detection limits in all pure water cells containing a lead form. Lead concentration levels in the leachate were controlled by lead form solubility and appeared to be a significant factor in influencing apparent leaching behavior. Surface analysis revealed surface crystals, which probably formed when soluble lead in the leachate reacted with dissolved or activated silica at the glass surface. The net effect was to reduce the release of some glass constituents to the leachate, although it was not clear whether the actual corrosion of the glass surface was reduced. Significantly different corrosion inhibiting effects were noted among lead metal and two forms of lead oxide.

Leaching behavior of nuclear waste glass heterogeneities

1986 ◽  
Vol 80 (1-3) ◽  
pp. 324-334 ◽  
Author(s):  
Zhu Bing-Fu ◽  
D.E. Clark ◽  
L.L. Hench ◽  
G.G. Wicks
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Leaching Behavior ◽  
Nuclear Waste Glass

Thermochemical Models for Nuclear Waste Glass Subsystems – MgO-CaO and MgO-Al2O3

1999 ◽  
Vol 556 ◽  
Author(s):  
T. M. Besmann ◽  
K. E. Spear ◽  
E. C. Beahm
Keyword(s):  
Phase Diagrams ◽  
Nuclear Waste ◽  
Equilibrium Phase ◽  
Supercooled Liquid ◽  
Liquid Solution ◽  
Waste Glass ◽  
Ternary Oxide ◽  
Nuclear Waste Glass ◽  
Associate Species ◽  
Glass Compositions

AbstractA relatively simple model, the associate species model, is being applied to nuclear waste glass compositions in order to accurately predict behavior and thermodynamic activities in the material. In the model, the glass is treated as a supercooled liquid, with the liquid species allowed to exist below their melting point. The approach requires an initial assembly of binary and ternary oxide liquid solution data that sufficiently reproduce the equilibrium phase diagrams. Two binary oxide subsystems, MgO-CaO and MgO-Al2O3, have been modeled and results compared to published phase diagrams. Computed activities of the glass constituent species are plotted as a function of composition at 1200°C.

Comparative Study of Seven Glasses for Solidification of Nuclear Wastes

1981 ◽  
Vol 11 ◽  
Author(s):  
J. L. Nogues ◽  
L. L. Hench ◽  
J. Zarzycki
Keyword(s):  
Comparative Study ◽  
Melting Temperature ◽  
Borosilicate Glasses ◽  
Nuclear Wastes ◽  
Process Variables ◽  
Leaching Behavior ◽  
Waste Products ◽  
Simulated Waste ◽  
High Level ◽  
Alkali Borosilicate Glasses

The relative leaching behavior of seven alkali borosilicate glasses considered for immobilization of high level radioactive wastes was compared using a static 90°C leach test similar to MCC-l. All compositions (Table I) were compatible with the low melting temperature, 1150*C, viscosity and other process variables required for the French AVM process. The quantity of simulated waste products was from 10.9-15.9 weight %.

Infrared Spectroscopy Structural Analysis of Corroded Nuclear Waste Glass K-26

2008 ◽  
Author(s):  
Sergey Stefanovsky ◽  
Alexander Barinov ◽  
Galina Varlakova ◽  
Irene Startseva ◽  
Michael I. Ojovan
Keyword(s):  
Infrared Spectroscopy ◽  
Structural Analysis ◽  
Nuclear Waste ◽  
Waste Glass ◽  
Nuclear Waste Glass

scholarly journals History of Nuclear Waste Glass in France

2014 ◽  
Vol 7 ◽  
pp. 3-9 ◽  
Author(s):  
Étienne Vernaz ◽  
Jérôme Bruezière
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Nuclear Waste Glass ◽  
History Of

Hydrotalcite Formed by Alteration of R7T7 Nuclear Waste Glass and Basaltic Glass in Salt Brine at 190°C

1993 ◽  
Vol 333 ◽  
Author(s):  
A. Abdelouas ◽  
J. L. Crovisier ◽  
W. Lutze ◽  
R. Müller ◽  
W. Bernotat
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Aluminium Content ◽  
Basaltic Glass ◽  
Alteration Product ◽  
Nuclear Waste Glass ◽  
Salt Brine ◽  
High Aluminium ◽  
Early Alteration

ABSTRACTThe R7T7 and synthetic basaltic glasses were submitted to corrosion in a saline MgCl2dominated solution at 190°C. For both glasses, the early alteration product is a hydrotalcite-like compound in which HPO42-, SO4-2and Cl-substitutes to CO32. The measured d003spacing is 7.68 Å for the hydrotalcite formed from R7T7 glass and 7.62 Å 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.

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