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| Preface | |
| Acknowledgments | |
| Materials Research Society Symposium Proceedings | |
| The Chemical Behavior of Transuranium Elements and Barrier Functions in Natural Aquifer Systems | p. 3 |
| Spent Fuel | |
| Kinematics and Thermodynamics of Non-Stoichiometric Oxidation Phase Transitions in Spent Fuel | p. 25 |
| Electrochemical Studies of Corrosion of Simfuel: Simulated Used UO[subscript 2] Fuel | p. 35 |
| Measurements of Grain-Boundary Inventories of [superscript 137]Cs, [superscript 90]Sr and [superscript 99]Tc in Used Candu Fuel | p. 41 |
| Effects of Air Oxidation on the Dissolution Rate of LWR Spent Fuel | p. 47 |
| Photothermal Deflection Spectroscopy Investigations of Uranium Electrochemistry | p. 55 |
| Kinetically Controlled Dissolution of UO[subscript 2](s) Under Oxidizing Conditions. A Combined Dissolution-Oxidation Model | p. 61 |
| Dissolution of UO[subscript 2](s) in MgCl[subscript 2]-Brines Under Different Redox Conditions | p. 67 |
| The Importance of Criticality in the Safety Analysis of the Spent-fuel Waste Container | p. 73 |
| Glass and Crystalline Waste Forms | |
| Initial Demonstration of the Vitirification of High-Level Nuclear Waste Sludge Containing an Organic Cs-Loaded Ion-Exchange Resin | p. 81 |
| Redox Systematics in Model Glass Compositions from West Valley | p. 87 |
| Leach Resistance Properties and Release Processes for Salt-Occluded Zeolite A | p. 95 |
| Catalytic Effect of Some Oxides on Calcination of Sodium Nitrate | p. 103 |
| Quantitative X-Ray Diffraction Analysis of Titanate Waste Forms and its Application to Damage Ingrowth | p. 109 |
| Fundamental Study on the Solidification of Cs[superscript +] and Sr[superscript 2+] with Hydrous [actual symbol not reproducible] Oxide Modified with Si and Zr | p. 117 |
| Incorporation of Radionuclides into Mineral Phases Via a Thermally Unstable Complexant Ligand | p. 123 |
| Uranium and Rare Earth Partitioning in Synroc | p. 129 |
| The Reaction of SRL 202 Glass in J-13 and DIW | p. 137 |
| Glass Performance: Mechanisms and Models | |
| The Leaching of Pu, Am, Np and Tc from High-Level Waste Glasses in Clay Media | p. 147 |
| Plutonium Leaching from a Reference Nuclear Waste Glass in Synthetic Interstitial Claywater | p. 155 |
| Enhancement of the Glass Corrosion in the Presence of Clay Minerals: Testing Experimental Results with an Integrated Glass Dissolution Model | p. 163 |
| Dissolution of R7T7 Glass in Static and Flowing Conditions: Influence of Si Diffusion Mechanism in the Leached Layer | p. 171 |
| Effects of MgO on the Short- and Long-Term Stability of R7T7 and M7 Nuclear Waste Glass on Aqueous Media | p. 177 |
| Effects of Radiation Exposure on Glass Alteration in a Steam Environment | p. 183 |
| Effects of [alpha]-Decay on Mechanical Properties of Simulated Nuclear Waste Glass | p. 191 |
| Analytical Electron Microscopy Study of Colloids from Nuclear Waste Glass Reaction | p. 199 |
| Does Fully Radioactive Glass Behave Differently Than Simulated Waste Glass? | p. 207 |
| Coupled Process Modeling and Waste-Package Performance | p. 215 |
| High-Level Nuclear-Waste Borosilicate Glass: A Compendium of Characteristics | p. 225 |
| Cementitious Materials | |
| Evaluation of Some Low-Activation Structural Materials for Minimizing Radioactive Waste Production by Future Nuclear Fusion Power Plants | p. 235 |
| Effects of Relative Surface Area and Leachant Composition on the [superscript 137]Cs Leach Rate from Cement Waste Forms | p. 241 |
| The Role of Oxygen Diffusion in the Release of Technetium from Reducing Cementitious Waste Forms | p. 247 |
| Alkali-Activated Fly Ash-Slag Cement Based Nuclear Waste Forms | p. 255 |
| The Possibility for Microbially Influenced Degradation of Cement Solidified Low-Level Radioactive Waste Forms | p. 261 |
| Effects of Microorganisms Growth on the Long-Term Stability of Cement and Bitumen | p. 267 |
| Borate Substituted Ettringites | p. 273 |
| Mobility of Chelated Radionuclides in Engineered Concrete Barriers | p. 279 |
| The Radiation Stability of Ground Granulated Blast Furnace Slag/Ordinary Portland Cement Grouts Containing Organic Admixtures | p. 285 |
| In-Situ Electrochemical Characterization of Grouted Radioactive Waste | p. 291 |
| Use of Fly-Ash for Sealing a Radioactive Waste Repository | p. 297 |
| Solidification of Microbiologically Treated Ion-Exchange Resins Using Portland Cement-Based Systems | p. 303 |
| Container Alteration | |
| Crevice Corrosion - NaCl Concentration Map for Grade-2 Titanium at Elevated Temperature | p. 311 |
| Corrosion of Stainless Steel for HLW Containers Under Gamma Irradiation | p. 317 |
| Effects of Chloride, Bromide, and Thiosulfate Ions on the Critical Conditions for Crevice Corrosion of Several Stainless Alloys as a Material for Geological Disposal Packages for Nuclear Waste | p. 323 |
| Critical Conditions for Initiation of Localized Corrosion of Mild Steels in Contact with Bentonite Used in Geological Disposal Packages of Nuclear Waste | p. 329 |
| Laboratory Studies of Gas Generation for the Waste Isolation Pilot Plant | p. 335 |
| Microbiologically Influenced Corrosion | |
| Recent Advances in the Study of Microbiologically Influenced Corrosion | p. 343 |
| Susceptibility of Stainless Steel Weldments to Microbiologically Influenced Corrosion | p. 353 |
| Principles of the Selection of Effective and Economic Corrosion-Resistant Alloys in Contact with Biologically Active Environments | p. 361 |
| The Use of Image Analysis in Long-Term Nondestructive Corrosion Monitoring of Nuclear Alloys | p. 369 |
| Use of Sputter-Deposited 316L Stainless Steel Ultrathin Films for Microbial Influenced Corrosion Studies | p. 381 |
| Near-Field Interactions | |
| Dealing with Uncertainty in the Chemical Environment in Bentonite Backfill | p. 389 |
| Aqueous Diffusion in Repository and Backfill Environments | p. 395 |
| Study on Retardation Mechanism of [actual symbol not reproducible] in Compacted Sodium Bentonite | p. 403 |
| Diffusion of Uranium in Compacted Sodium Bentonite | p. 409 |
| Temperature and Moisture Distributions in a Clay Buffer Material Due to Thermal Gradients | p. 417 |
| Moisture Adsorption and Volume Change of Partially Saturated Bentonite Buffer Materials | p. 425 |
| Radiolytically-Induced Gas Production in Plutonium-Spiked WIPP Brine | p. 431 |
| Analysis of Evaporation in Nuclear Waste Boreholes in Unsaturated Tuff | p. 439 |
| Compared Study of Radiolysis-Induced Gas Liberation in Rocksalt from Various Origins | p. 447 |
| Radiation Damage in NaCl: Calculations with an Extended Jain-Lidiard Model | p. 453 |
| Evaluation of the Retention Capability of Backfill Materials in the Presence of Cement Waste Form | p. 459 |
| Diffusion of Corrosion Products of Iron in Compacted Bentonite | p. 467 |
| Study of the Performance of Sealing Systems for Access Shafts in a High-Level Waste Repository | p. 475 |
| Results from Simulated Remote-Handled Transuranic Waste Experiments at the Waste Isolation Pilot Plant (WIPP) | p. 481 |
| Natural Analogues | |
| Modelling In-Situ Matrix Diffusion at Palmottu Natural Analogue Study Site in SW Finland | p. 489 |
| Uranium Mineral - Groundwater Equilibration at the Palmottu Natural Analogue Study Site, Finland | p. 497 |
| Oxidative Alteration of Uraninite at the Nopal I Deposit, Mexico: Possible Contaminant Transport and Source Term Constraints for the Proposed Repository at Yucca Mountain | p. 505 |
| The Alteration of Uraninite to Clarkeite | p. 513 |
| Kinetic Studies of Natural Uranium Minerals for the Long-Term Evolution of Spent Nuclear Fuel Under Oxidizing Conditions | p. 521 |
| A Modelling Study on the Fractionation of Uranium Among Minerals During Rock Weathering | p. 527 |
| A Modelling Study of the Effect of Rock Alteration on the Redistribution of Uranium | p. 535 |
| Surface-Discharging Hydrothermal Systems at Yucca Mountain - Examining the Evidence | p. 543 |
| Corrosion Model Validation in High Level Nuclear Waste Package Research | p. 549 |
| Long-Term Prediction for Engineered Barriers | |
| The Long-Term Performance of Nuclear Waste Forms: Natural Materials - Three Case Studies | p. 559 |
| Accelerated Glass Reaction Under PCT Conditions | p. 569 |
| Modeling Surface Area to Volume Effects on Boro-Silicate Glass Dissolution | p. 577 |
| Increases in Leach Rate Due to Possible Cracking in Silicate Glasses | p. 583 |
| Observation by SEM/EDXS of Leached Layers on SRL-165 Glass from 5-Year MIIT Test | p. 591 |
| A Justification for the Use of Data from Accelerated Leach Tests of Glass | p. 599 |
| Ancient Metallurgy and Nuclear Waste Containment | p. 605 |
| Long-Term Predictions Relating to Environment Sensitive Cracking | p. 613 |
| The Potential Role of Diffusion-Induced Grain-Boundary Migration in Extended Life Prediction | p. 625 |
| Experiments and Modelling Studies Concerning Localised Corrosion of Carbon Steel and Stainless Steel Containers for Intermediate- and Low-Level Radioactive Waste | p. 637 |
| Repassivation Potentials for Long-Term Life Prediction of Localized Corrosion | p. 649 |
| Performance Assessment of Engineered Barrier Systems | |
| The Engineered Barrier System: Performance Issues | p. 657 |
| Progress in Waste Package and Engineered Barrier System Performance Assessment and Design | p. 663 |
| Some Important Mechanisms and Processes in the Near Field of the Swedish Repository for Spent Nuclear Fuel | p. 675 |
| Performance Assessment of Engineered Barriers Using the Vault Model | p. 689 |
| Key Issues Influencing the Performance of Near-Field Barriers | p. 697 |
| Research Needs in HLW Disposal Programmes | p. 707 |
| The IAEA Coordinated Research Programme on the Performance of High-Level Waste Forms and Packages Under Repository Conditions | p. 719 |
| The Near-Field Transport Code Tullgarn and its Use in Performance Assessment | p. 725 |
| Near-Field Performance Assessment for the Saltstone Disposal Facility | p. 731 |
| Radionuclide Chemistry and Transport | |
| Bulk Solubility and Speciation of Plutonium(VI) in Phosphate-Containing Solutions | p. 739 |
| Evidence of Radiolytic Oxidation of [superscript 241]Am in [actual symbol not reproducible] Media | p. 747 |
| Thermodynamic Modelling of the Effect of Hydroxycarboxylic Acids on the Solubility of Plutonium at High pH | p. 753 |
| A Comparative Study of Europium, Thorium and Uranium Binding to an Aquatic Fulvic Acid | p. 759 |
| The Role of Siderophores in the Transport of Radio-Nuclides | p. 765 |
| Microbial Effects on the Radionuclide Transport in a Deep Nuclear Waste Repository | p. 771 |
| Experimental Study of Uranium(6+) Sorption on the Zeolite Mineral Clinoptilolite | p. 777 |
| Radionuclide Sorption Modeling Using the MINTEQA2 Speciation Code | p. 783 |
| Measurements of Metal Adsorption in Oxide-Clay Mixtures: "Competitive-Additivity" Among Mixture Components | p. 791 |
| Transport of Neptunium Through Yucca Mountain Tuffs | p. 797 |
| Radionuclide Migration Studies on Tonalite | p. 803 |
| Radio-Labelled Humic Materials in Migration Studies | p. 811 |
| Colloid Properties in Granitic Groundwater Systems, with Emphasis on the Impact on Safety Assessment of a Radioactive Waste Repository | p. 817 |
| The Influence of Non-Linear Sorption on Colloid Facilitated Radionuclide Transport Through Fractured Media | p. 825 |
| Transport Modeling in a Finite Fractured Rock Domain | p. 831 |
| Direct Determination of Transport Parameters in Repository Materials | p. 839 |
| Diffusivity and Porosity in Rock Matrix - Laboratory Methods Using Artificial and Natural Tracers | p. 845 |
| Development of a Gas Method for Migration Studies in Fractured and Porous Media | p. 851 |
| BNFL Lysimeter Programme to Investigate the Leaching of Radionuclides from Low-Level Radioactive Waste | p. 857 |
| Pilot and Field-Scale Uranium Lysimeter Studies at the Oak Ridge Y-12 Plant | p. 865 |
| Performance Assessment of Geological Systems | |
| Is It Possible to Demonstrate Compliance with the Regulations for High-Level-Waste Repositories? | p. 873 |
| Conceptual Structure of Performance Assessments Conducted for the Waste Isolation Pilot Plant | p. 885 |
| Iterative Performance Assessment for the Greater Confinement Disposal Facilities: Preliminary Results of Round Two | p. 899 |
| Model Validation and Decision Making: An Example Using the Twin Lakes Tracer Test | p. 909 |
| Uncertainty and Sensitivity Analyses of Groundwater Travel Time in a Two-Dimensional Variably-Saturated Fractured Geologic Medium | p. 921 |
| Effects of Some Common Geological Features on Two-Dimensional Variably Saturated Flow | p. 929 |
| A Demonstration of Dose Modeling at Yucca Mountain | p. 937 |
| The Use of Formal and Informal Expert Judgments When Interpreting Data for Performance Assessments | p. 943 |
| Approaches to Long-Term Performance Assessment of Deep Underground Disposal of Radioactive Wastes: A European Perspective | p. 951 |
| Author Index | p. 963 |
| Subject Index | p. 967 |
| Table of Contents provided by Blackwell. All Rights Reserved. |
ISBN: 9781558991897
ISBN-10: 1558991891
Series: MRS Proceedings
Audience:
General
Format:
Hardcover
Language:
English
Number Of Pages: 951
Published: 26th March 1993
Publisher: Materials Research Society
Dimensions (cm): 24.1 x 16.5
x 4.4
Weight (kg): 1.0
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