Effects of Flow Parameters on the Leaching of Nuclear Waste Glass

1984 ◽  
Vol 44 ◽  
Author(s):  
R. B. Adiga ◽  
E. P. Akomer ◽  
D. E. Clark
Keyword(s):  
Nuclear Waste ◽  
Flow Rate ◽  
Volume Ratio ◽  
Water Volume ◽  
Leaching Rate ◽  
Leaching Behavior ◽  
Waste Package ◽  
Flow Parameters ◽  
Nuclear Waste Glass ◽  
Independent Effects

Environmental conditions in a repository are expected to be significantly different from those encountered by a glass tested under MCC-1 specifications. In addition to variations in flow rate and glass surface area to water volume ratio (SA/V), the water chemistry and presence of waste package components in the repository will most certainly affect the leaching behavior of the glass. The independent effects of each of these variables have been studied by numerous investigators. For example, it is well known that the leaching rate increases as the flow rate increases (1). Also, the rate of approach to saturation is increased as SA/V is increased under MCC-1 type testing (2). The use of silicate water generally decreases the rate of leaching while waste package components such as iron enhances the leaching rate of glass under MCC-1 type testing (3–4).

Leach Models for a Commercial Nuclear Waste Glass

1982 ◽  
Vol 15 ◽  
Author(s):  
William L. Kuhn ◽  
Richard D. Peters
Keyword(s):  
Nuclear Waste ◽  
Protective Layer ◽  
Volume Ratio ◽  
Surface Processes ◽  
Reaction Products ◽  
Leaching Behavior ◽  
Rate Laws ◽  
Nuclear Waste Glass ◽  
Soluble Species ◽  
Effect Of Surface

ABSTRACTA review of the leaching behavior of 76–68 glass shows that it cannot be explained in terms of diffusion in the glass, which has been the basis for several leach models. Instead, we present two models based on a dissolution rate impeded by surface processes: the accumulation of a protective layer of insoluble reaction products, and adsorption of reaction products on the surface. The resulting predicted time dependences are identical and predict a change from linear to parabolic rate laws for soluble species, which is found to agree with the data over a range of temperatures. Incongruent release is attributed primarily to solubility effects. The relative merits of the models are discussed on the basis of the effect of surface area-to-volume ratio in static leach tests. Their relevance to modeling repository behavior is discussed.

Materials Interactions Relating to Long-Term Geologic Disposal of Nuclear Waste Glass

1986 ◽  
Vol 84 ◽  
Author(s):  
Ned E. Bibler ◽  
Carol M. Jantzen
Keyword(s):  
Nuclear Waste ◽  
Review Paper ◽  
Waste Glass ◽  
Waste Form ◽  
Glass Waste ◽  
Waste Package ◽  
Geologic Disposal ◽  
Nuclear Waste Glass ◽  
Backfill Materials

AbstractIn the geologic disposal of nuclear waste glass, the glass will eventually interact with groundwater in the repository system. Interactions can also occur between the glass and other waste package materials that are present. These include the steel canister that holds the glass, the metal overpack over the canister, backfill materials that may be used, and the repository host rock. This review paper systematizes the additional interactions that materials in the waste package will impose on the borosilicate glass waste form-groundwater interactions. The repository geologies reviewed are tuff, salt, basalt, and granite. The interactions emphasized are those appropriate to conditions expected after repository closure, e.g. oxic vs. anoxic conditions. Whenever possible, the effect of radiation from the waste form on the interactions is examined. The interactions are evaluated based on their effect on the release and speciation of various elements including radionuclides from the glass. It is noted when further tests of repository interactions are needed before long-term predictions can be made.

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

237Np aND 239Pu Solution Behavior During Hydrothermal Testing of Simulated Nuclear Waste Glass with Basalt and Steel

1984 ◽  
Vol 44 ◽  
Author(s):  
Janet A. Schramke ◽  
Scott A. Simonson ◽  
David G. Coles
Keyword(s):  
Nuclear Waste ◽  
Cast Steel ◽  
Size Fraction ◽  
Weight Ratio ◽  
Reaction Products ◽  
Solid Materials ◽  
Solution Behavior ◽  
Waste Package ◽  
Hydrothermal Experiments ◽  
Nuclear Waste Glass

AbstractA series of hydrothermal experiments were carried out on 237Np- and 239Pu-doped PNL 76–68 glass, synthetic basalt groundwater, basalt, and cast steel. These hydrothermal experiments are part of the Basalt Waste Isolation Project investigation of the interactions of waste package components in a basalt repository. Experiments of three months duration were conducted in Dickson-type rocking autoclaves at 200°C and 30 MPa, with an initial fluid to solid weight ratio of 10:1. All solid materials were ground and sieved to a narrow size fraction. The experiments carried out were: glass and groundwater; glass, basalt, and groundwater; glass, steel, and groundwater; and glass, steel, basalt, and groundwater. Unfiltered, 4000 Â filtered, and 18 Å filtered solutions were analyzed to determine the concentrations of radionuclides in solution and those associated with colloids.The quantities of 237Np and 239Pu in solution were very small. Worstcase calculations indicate that 0.01% or less of the total radionuclide inventories were present in solution. The highest solution concentrations of the actinide dopants were observed in the experiments with basalt, even though smaller amounts of glass were dissolved than in the experiments without basalt. The observed differences in the solution concentrations of 237Np and 239Pu were probably controlled by differences in the reaction products, which were clinoptilolite in the experiments with basalt, and an Fe-Zn smectite clay in the experiments without basalt.

A Kinetic Model of Nuclear Waste Glass Dissolution in Flowing Water Environments

1984 ◽  
Vol 44 ◽  
Author(s):  
Aaron Barkatt ◽  
Barbara C. Gibson ◽  
Marek Brandys
Keyword(s):  
Kinetic Model ◽  
Nuclear Waste ◽  
Flow Rate ◽  
Flowing Water ◽  
Flow Rates ◽  
Glass Dissolution ◽  
Nuclear Waste Glass ◽  
Simple Kinetic Model ◽  
Leachate Composition ◽  
Flow Experiments

AbstractA simple kinetic model for the description of the interaction of nuclear waste borosilicate glass with water has been developed. In the case of SRL TDS-131 glass leached in water at 70°C over a broad range of flow rates this model was found useful both in describing the evolution of leachate composition as a function of exposure time at a particular flow rate and in describing the dependence of the steady-state concentrations of the leached elements in solution on flow rate in a series of flow experiments.

Role of Surface Layers in the Leaching Behavior of Glass

1988 ◽  
Vol 125 ◽  
Author(s):  
B.K. Zoitos ◽  
D.E. Clark
Keyword(s):  
Surface Layer ◽  
Nuclear Waste ◽  
Surface Composition ◽  
Analytical Techniques ◽  
Surface Layers ◽  
Leaching Behavior ◽  
Leach Rate ◽  
Layer Analysis ◽  
Nuclear Waste Glass

ABSTRACTResults are presented from a two-year dynamic leach test of nuclear waste glass under conditions designed to simulate those of the Stripa granite repository. Solution and surface analytical techniques were used to assess the glass leach rate as well as surface composition and morphology. Glass leach rates were observed to decrease by a factor of two during the first six months. This effect is attributed to the formation of a protective surface layer. Analysis of this layer shows it to be rich in silicon and iron and depleted in lithium, sodium and boron. It was also found that the layer is subject to dissolution.

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.

scholarly journals The Role of Laboratory Analog Experiments in Assessing the Performance of Waste Package Materials

1990 ◽  
Vol 212 ◽  
Author(s):  
James C. Cunnane ◽  
John K. Bates
Keyword(s):  
Volume Ratio ◽  
Reaction Rates ◽  
Waste Glass ◽  
System Level ◽  
Water Volume ◽  
Small Scale ◽  
Analog Testing ◽  
Waste Package ◽  
Laboratory Analog ◽  
Package Materials

ABSTRACTThere is an immediate need to begin to validate models that can be used for assessing the performance of waste package materials in an unsaturated repository environment. This paper examines available testing information and testing approaches that could support validation of models for engineering barrier system (EBS) radionuclide release. The content is presented in the context of the general methodology that has been proposed for validating performance assessment models [1], Available experimental observations are used to test some of the EBS release rate modeling premises. These observations include evidence of fluid film formation on waste glass surfaces in isothermal humid environments, accelerated waste glass reaction rates under repository service conditions of large glass surface area to water volume ratio, and mobilization of radionuclides as solutes and colloids. It is concluded that some important modeling premises may not be consistent with available experimental Information. However, it is also concluded that future laboratory testing, which simulates the Integrated waste package system (i.e., laboratory analog testing), is needed to evaluate the significance of these Inconsistencies and to test the system level models. A small-scale apparatus which was developed and tested to examine the feasibility of laboratory analog testing for the unsaturated Yucca Mountain repository environment is described.

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

Study of The Influence of Different Variables on Clathrate Practical Applications in Phenol Removal

2020 ◽  
Vol 38 (9A) ◽  
pp. 1373-1383
Author(s):  
Riyadh S. AL- Mukhtar ◽  
Shurooq T. Remedhan ◽  
Marwa N. Hussin
Keyword(s):  
Crystal Structures ◽  
High Capacity ◽  
Volume Ratio ◽  
Constant Speed ◽  
Water Volume ◽  
Phenol Removal ◽  
Process Performance ◽  
Economic Costs ◽  
Practical Applications ◽  
Glass Cell

In this work, effluent wastewater treated by using cyclopentane-water Clathrate system to treat water contaminates with phenols at concentrations (300, 250, 200, 150, 100 and 50) ppm in order to investigate the capability of process performance. Clathrate or hydrate are strong crystal structures including water (host particles) and little particles (guest particles). The experiments were conducted at different cyclopentane-water volume ratios (1: 2 and 1: 4). The work was done in a 250 ml glass cell with an electric mixer at a constant speed of 280 cycles per minute. Phenol was highest removal percent at 300ppm at 1: 4volume ratio was (92.3%), while the lowest concentration at 50 ppm and 1: 2volume ratio was (55%). Yield and Enrich factor had the highest values at the lowest concentration 50ppm and 1:2 volume ratio were (85% and 2.42) respectively. The technique of the Clathrate proved that it has a high capacity in the separation and achieve high removal percentage compared to other methods at standard conditions when the pressure of 1 atmosphere and temperature higher than the degree of freezing water and less economic costs compared to other methods.

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