Induced Near-Hydrothermal Alteration Studies on Nuclear Waste Glass and Natural Analogue (Obsidian) for Performance Assessment in Geological Repository

2012 ◽  
pp. 285-306
Author(s):  
Nishi Rani ◽  
J. P. Shrivastava ◽  
R. K. Bajpai
Keyword(s):  
Performance Assessment ◽  
Hydrothermal Alteration ◽  
Nuclear Waste ◽  
Waste Glass ◽  
Natural Analogue ◽  
Geological Repository ◽  
Nuclear Waste Glass

Hydrothermal alteration of a simulated nuclear waste glass: effects of a thermal gradient and of a chemical barrier

1996 ◽  
Vol 8 (3) ◽  
pp. 533-548 ◽  
Author(s):  
Christophe Poinssot ◽  
Bruno Goffé ◽  
Marie-Claude Magonthier ◽  
Pierre Toulhoat
Keyword(s):  
Hydrothermal Alteration ◽  
Nuclear Waste ◽  
Thermal Gradient ◽  
Waste Glass ◽  
Nuclear Waste Glass

Modeling the Durability of Silica Additives Proposed to Protect Nuclear Waste Glass Packages in A Geological Repository

1999 ◽  
Vol 556 ◽  
Author(s):  
Yves Minet ◽  
Étienne Vernaz
Keyword(s):  
Nuclear Waste ◽  
Transport Model ◽  
Waste Glass ◽  
One Dimensional ◽  
Adsorption Sites ◽  
Geological Repository ◽  
Nuclear Waste Glass ◽  
The Media ◽  
Rhone Valley ◽  
Silica Additive

AbstractSilica additives have been proposed to protect nuclear waste glass packages in deep geological repositories by presaturating silicon adsorption sites* in the media surrounding the package (engineered barrier, canister and overpack corrosion products). The durability of such additives was estimated using a one-dimensional dissolution-transport model developed at the CEA's Rhône Valley Research Center for the French reference glass in typical disposal sites. The silica additive would be placed between the wasteform and the overpack and thus dissolved before the waste glass. Its lifetime is proportional to Madd2(where Madd is the added silica mass) up to a critical value Mcrit at which it increases considerably (from 103 or 104 to 108 years) due to saturation of the adsorption sites. Excess silica consumption is then limited by the typically very low (3 × 10−3 l·m−2y−1 ) groundwater flow in the geological site. After consumption of the added silica, the evolution of the altered waste glass fraction is comparable to the evolution without added silica if Madd « Mcrit, but much lower if Madd ≈ Mcrit or Madd > Mcrit. These findings were confirmed by some experimental evidence, and establish that a few kilograms of added silica for a 400 kg package can considerably enhance the waste glass durability.

A natural analogue of nuclear waste glass in compacted bentonite

2000 ◽  
Vol 15 (2) ◽  
pp. 141-155 ◽  
Author(s):  
Gento Kamei ◽  
Yasuhisa Yusa ◽  
Takashi Arai
Keyword(s):  
Nuclear Waste ◽  
Waste Glass ◽  
Natural Analogue ◽  
Compacted Bentonite ◽  
Nuclear Waste Glass

Temperature Dependence of R7T7 Nuclear Waste Glass Alteration Mechanisms

1987 ◽  
Vol 112 ◽  
Author(s):  
E. Y. Vernaz ◽  
J L. Dussossoy ◽  
S. Fillet
Keyword(s):  
Activation Energy ◽  
Temperature Dependence ◽  
Hydrothermal Alteration ◽  
Nuclear Waste ◽  
Waste Glass ◽  
Hydration Mechanism ◽  
Nuclear Waste Glass ◽  
High Concentrations ◽  
Corrosion Mechanisms

AbstractThe French LWR reference glass R7T7 was leached at temperatures between 100°C and 300°C at a pressure of 10 MPa.An activation energy of 25 kJ/mole was found between 100°C and 250°C which is different from the 60 kJ/mole previously found between 25°C and 70°C. It is suggested that a potential glass hydration mechanism becomes predominant when dissolution is significantly slowed by high concentrations of silica in solution. At 300°C, a complete change in the corrosion mechanisms is found as the glass undergoes a rapid hydrothermal alteration

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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