scholarly journals Experimental Hydration Studies of Natural and Synthetic Glasses

1988 ◽  
Vol 125 ◽  
Author(s):  
John K. Bates ◽  
Teofilo A. Abrajano ◽  
William L. Ebert ◽  
James J. Mazer ◽  
Thomas J. Gerding
Keyword(s):  
Nuclear Waste ◽  
Saturated Vapor ◽  
Hydrothermal Solution ◽  
Reaction Rates ◽  
Physical Processes ◽  
Laboratory Methods ◽  
Natural Processes ◽  
Nuclear Waste Glass ◽  
Reaction Processes ◽  
Hawaiian Basalt

ABSTRACTThe results of a series of hydration experiments on natural glasses (Hawaiian basalt, obsidian) and the nuclear waste glass WV-44 done to examine laboratory methods of accelerating reaction processes are summarized. The glasses were reacted in hydrothermal solution and in saturated vapor water. It was found that different reaction rates and processes were found using the differing conditions, and that laboratory efforts to accelerate and duplicate natural processes must account for the physical processes that occur naturally.

scholarly journals Experimental Hydration Studies of Natural and Synthetic Glasses

1988 ◽  
Vol 123 ◽  
Author(s):  
John K. Bates ◽  
Teofilo A. Abrajano ◽  
William L. Ebert ◽  
James J. Mazer ◽  
Thomas J. Gerding
Keyword(s):  
Nuclear Waste ◽  
Saturated Vapor ◽  
Hydrothermal Solution ◽  
Reaction Rates ◽  
Physical Processes ◽  
Laboratory Methods ◽  
Natural Processes ◽  
Nuclear Waste Glass ◽  
Reaction Processes ◽  
Hawaiian Basalt

AbstractThe results of a series of hydration experiments on natural glasses (Hawaiian basalt, obsidian) and the nuclear waste glass WV-44 done to examine laboratory methods of accelerating reaction processes are summarized. The glasses were reacted in hydrothermal solution and in saturated vapor water. It was found that different reaction rates and processes were found using the differing conditions, and that laboratory efforts to accelerate and duplicate natural processes must account for the physical processes that occur naturally.

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.

scholarly journals Does Fully Radioactive Glass Behave Differently than Simulated Waste Glass?

1992 ◽  
Vol 294 ◽  
Author(s):  
X. Feng ◽  
J. K. Bates ◽  
C. R. Bradley ◽  
E. C. Buck
Keyword(s):  
Radiation Field ◽  
Nuclear Waste ◽  
Potassium Feldspar ◽  
Waste Glass ◽  
Solution Ph ◽  
Static Tests ◽  
Leach Rate ◽  
Nuclear Waste Glass ◽  
Surface Alteration ◽  
Leach Behavior

ABSTRACTStatic tests at SA/V (ratio of surface area of glass to solution volume) 20,000 m−1 on SRL 200 glass compositions show that, at long test periods, the simulated nuclear waste glass (nonradioactive) leaches faster than the corresponding radioactive glass by a factor of about 40, although comparative tests, done through 560 days, at lower SA/V, 2000 m−1, indicate little difference in the leach behavior of the two types of glasses. The similarity in leach behavior between radioactive and simulated glasses at SAN of 2000 m−1 or lower is also observed for SRL 165/42 and 131/11 compositions. The accelerated glass reaction with the simulated glass 200S is associated with the formation of crystalline phases such as clinoptilolite (or potassium feldspar), and a pH excursion. The radiation field generated by the fully radioactive glass reduces the solution pH. This lower pH, in turn, may retard the onset of increased reaction rate. The radiation field generated by the radioactive glasses does not directly affect the stability of the glass surface alteration layer under those conditions where the radioactive and simulated glasses react at the same rate. These results suggest that the fully radioactive nuclear waste glass 200R may maintain a much lower leach rate than the simulated 200S, if the lower pH in the 200R leachate can be sustained. Meaningful comparison tests between radioactive and simulated nuclear waste glasses should include long-term and high SA/V tests.

scholarly journals THE TRANSMUTATION MODELING FOR PLUTONIUM AND MINOR ACTINIDES IN THE TWO-ZONE SUBCRITICAL REACTOR

2019 ◽  
pp. 83-87
Author(s):  
V.I. Gulik ◽  
D.O. Sheliahovskyi ◽  
A.V. Nosovskyi
Keyword(s):  
Nuclear Waste ◽  
Reaction Rates ◽  
Fast Neutrons ◽  
Minor Actinides ◽  
Capture Reaction ◽  
Thermal And Fast Neutrons ◽  
Subcritical System ◽  
Subcritical Reactor

The investigations directed to plutonium and minor actinides transmutations for two-zone subcritical reactor is considered in present paper. The distributions of thermal and fast neutrons in the subcritical system were obtained. The distributions of fission and capture reaction rates for 237Np and 243Am were analyzed from viewpoint of minor actinides transmutation. The transmutation simulations for different distributions of pin targets were carried out within the scope of this paper. The obtained modeling results for different nuclear waste isotopes were analyzed and discussed.

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