Migratory Properties of Some Nuclear Waste Elements in Geologic Media

Seitz, M.G.; Rickert, Paul G.; Fried, S.; Friedman, A.M.; Steindler, M. J.

doi:10.13182/nt79-a32262

Cited by 21 publications

(13 citation statements)

References 5 publications

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“…Many chemical species may coexist and differ from each other in the migration behaviour. Column techniques may be effective for the study of the migration behaviour and some experiments have been reported [8,9].…”

Section: Introductionmentioning

confidence: 99%

Column Experiments on Migration Behaviour of Neptunium (V)

et al. 1988

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Neptunium I Solubility / Hydrolysis /Migration /Quartz /Liquid chromatography SummaryTo examine the chemical forms of neptunium (V) in aqueous solutions, the solubility was measured by an ultrafiltration method. The existence of three species of NpOj, NpOjOH and NpOj (OH) 2 were expected from the resulting pH-dependent solubility curve. Their hydrolytic data were obtained as follows; log0, =5.7, log0 3 = 8.6 and log K sp = -10.7 at ionic strength of 0.01 M.A high performance liquid chromatography was applied to study the migration behaviour of neptunium (V) in a quartzpacked column. The presence of two components of neptunium (V) which were different from each other in the migration velocity was demonstrated successfully. The one component was the unretarded component moving with the eluent, and the other the retarded component. The distribution coefficient of the retarded component decreased with the increasing ionic strength of the eluent and increased with the increasing pH. Mechanisms of the migration behaviour are discussed for each component.

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Section: Introductionmentioning

confidence: 99%

Column Experiments on Migration Behaviour of Neptunium (V)

et al. 1988

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“…The strontium peaks were delayed relative to the advancing water front (which would traverse the column in the first 6.5 mL of eluent). Moreover, each of the strontium peaks seen in Figure 11, even the one produced with the slowest flow is wider than predicted by the peak width (2 mL full width at half maximum) that was seen for peaks of tritiated water that were eluded through the column (8) . Therefore, the strontium has interacted with the glauconite column and, as indicated by the different peak shapes, interacted differently at each flow.…”

Section: Strontium Migration Experiments __in_clnijconi_lmentioning

confidence: 81%

Nuclide Migration in Fractured or Porous Rock

Rickert

Strickert

Seitz

1979

ACS Symposium Series

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“…Obtaining an accurate count of activity on the solid may be difficult or impossible. Currently, no clear cut resolution to the container adsorption problem has been made, although the Argonne National Laboratory (Seitz et al 1978) introduced a novel approach of coring out crystalline rock and performing a IIrock test tube ll batch Kd experiment. From a practical standpoint, correcting for container adsorption as originally proposed should build in an element of conservatism.…”

Section: Static or Batch Kd Methodsmentioning

confidence: 99%

Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

Brandstetter¹,

Harwell²,

Howes³

et al. 1979

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Analysis 3-10 3.3 VTT Model Predicted Potentiometric Surface for the Large Region (7500 ft nodes) Paradox Simulation. Small Region Potentials are Illustrated in Figure 3.2. 3-11 3.4 Three-Dimensional Finite Element Representation of Groundwater Reservoir Beneath Long Island, New York 3-13 3.5 Aquatic Pathways of Exposure from Geologic Storage Site for SHLW. 3-20 4.1 Factors That Determined the Concentration of Radionuclides in Solutions Leached Through the Waste 4-3 4.2 Large Volume Sorption Curves for Americium on Basalt 4-4 4.3 Axial Filter 4-10 4.4 Distribution of Sr(II) Between Montmorillonite and Sodium Chloride-0.1 M Sodium Acetate Solutions (Low Loading Sr(II)-4-14 4.5 Elution of Strontium from a Column of Glauconite. Peak Width Increases with Flow Rate (Top of Bottom), Indicating Nonequilibium Behavior 4-16 4.6 Elution Curve for 85S r Forced Through an Oolitic Limestone Column with REW Solution. Solution Flow Rate was 0.1 ml/min. 4-18 4.7 Elution Curve for 85S r Forced Through an Oolitic Limestone Column with Recipe Solution. Solution Flow Rate was 0.043 ml/min 4-18 4.8 High Pressure Sorption Apparatus 4-19 xvii 4.9 Experimental and Predicted Distributions of Americium on the Fissure Surfaces after Elution with 20 Fissure Volumes of Solution at a Flow Rate of 1.13 cm h-1. .. • 4-21 4.10 Experimental and Predicted Distributions of Americium on the Fissure Surfaces after Elution with 20 Fissure Volumes of Solution at a Flow Rate of 4.77 cm h-1 4-21 4.11 Adsorption on Am-241 on Na-Montmorillonite 4.12 Loading Effect on Distribution Coefficient of Cobalt 4.13 Distribution Coefficients for Cd(II)/Na(I) Exchange Versus 4-28 4-28 Loading on Montmorillonite 4-29 4.14 Adsorption of Cs(I) on the Sodium Form of Montmorillonites From Several Sources. 4-31 4.15 Adsorption of Sr(II) on the Sodium Form of Wyoming Montmorillonite. 4-31 4.16 Adsorption of Ba(II) on the Sodium Form of Wyoming Montmorillonite. 4-32 4.17 Adsorption of Eu(III) on the Form of Wyoming Montmorillonite. 4-32 4.18 Effects of Loading on Distribution Coefficients of Cs(I) on the Sodium Form of Wyoming Montmorillonite 4-35 4.19 Effect of Loading on Distribution Coefficients of Sr(II) on the Sodium Form of Wyoming Montmorillonite 4-35 4.20 Effect of Loading on Distribution Coefficients of Eu(III) on the Sodium Form of Wyoming Montmorillonite 4.36 4.21 Log Kd Versus Loading for 1-1 Exchange • 4-89 4.22 Apparatus for Leach/Migration Experiments in Which Nuclides Leached from a Solidified Waste Form at Elevated Temperature Migrate in Rock Columns 4-93 4.23 Elution of Ionic and Particulate Tracers in the Large Column 4-95 4.24 Elution of Particulate Tracers in the Large and Small Columns 4-96 4.25 Elution of Ionic and Particulate Tracers in the Small Column 4-97 xviii TABLES 1.1 Potentially Disruptive Phenomena for Nuclear Waste Repositories 1-3 1.2 Some Example Input Data for the Pilot Model 1-21 2.1 Leaching Schedule for Doped Waste Glasses 2-4 2.2 Leach Solutions. 2-4 2.3 Chemical Composition of WIPP B Salt Brine 2-5 2.4 Composition of NFS (76-68) Glas...

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Migratory Properties of Some Nuclear Waste Elements in Geologic Media

Cited by 21 publications

References 5 publications

Column Experiments on Migration Behaviour of Neptunium (V)

Column Experiments on Migration Behaviour of Neptunium (V)

Nuclide Migration in Fractured or Porous Rock

Waste Isolation Safety Assessment Program. Technical progress report for FY-1978

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