Materials Research Society Symposium Proceedings Volume 663 Scientific Basis for Nuclear Waste Management XXIV Editors: Kaye P. Hart, Gregory R. Lumpkin Purchase this Volume: Order Online | Download Order Form

Sections

• Conditioning of Wastes
• Immobilization of Wastes in Cement and Bitumen
• Glass Wasteforms
• Ceramic Wasteforms
• Spent Fuel
• Canisters
• Engineered Barriers
• Microbiology and Thermodynamics
• Repository Studies
• Natural Systems
• Solubility, Transport Modeling and Migration

 

Conditioning of Wastes
	The Influence of Chemical Composition of Liquid Radioactive Waste on the Evaporation Process
	Pretreat: A Graphical User Interface-Based Spreadsheet Model for Hanford Tank Waste Pretreatment Processes
	Thermochemical Approach on Treating Spent Ion Exchange Resins
	High Level Liquid Waste Solidification Using a "Cold" Crucible Induction Melter
	Development and Characteristics of a New Porous Glass Crystalline Matrix (Gubka) for Stabilizing Radioactive and Hazardous Solutions
	Study Of BiPbO2NO3 for I-129 Fixation Under Reducing Conditions
	Iodine Immobilization by Sodalite Waste Form
	Technology and Equipment Based on Induction Melters with "Cold" Crucible for Reprocessing Active Metal Waste
	Ash and Soil Conditioning Using Exothermic Metallic Compositions

 

Immobilization of Wastes in Cement and Bitumen
	Behavior of High Performance Concrete Under High Temperature (60-450°C) for Surface Long-Term Storage: Thermo-Hydro-Mechanical Residual Properties
	Towards an Intrinsic Relationship between Diffusion Coefficients and Microscopic Features of Cements?
	Cs Speciation in Cements
	Sorption Behavior of Radionuclides on Calcium-Leached Mortar
	Cesium and Lead Uptake by CSH Phases of Hydrated Cement
	Categorization of Cement Hydrates by Radionuclide Sorption Mechanism
	In Situ Interaction Between Cement and Clay: Implications for Geological Disposal
	Long-Term Behavior of Bituminized Waste: Modeling of Auto-Irradiation and Leaching
	The Effect of Radiolytic Degradation Products of Eurobitum on the Solubility and Sorption of Pu and Am in Boom Clay

 

Glass Wasteforms
	Electrical Conductivity and Structural Properties of Cesium Iron Phosphate Glasses: A Potential Host for Vitrifying Nuclear Waste
	Influence of Platinum-Group Metals on Nuclear Glass Properties: Viscosity, Thermal Stability, and Alterability
	Neodymium Incorporation in Zirconolite-Based Glass-Ceramics
	Development of Zirconolite-Based Glass-Ceramics for the Conditioning of Actinides
	Development and Characterization of Borosilicate Glasses for Immobilization of Plutonium-Containing Alkaline Sludges
	Gadolinium Borosilicate Glass-Bonded Gd-Silicate Apatite: A Glass-Ceramic Nuclear Waste Form for Actinides
	Protective Effect of the Alteration Gel: A Key Mechanism in the Long-Term Behavior of Nuclear Waste Glass
	Apparent Solubility Limit of Nuclear Glass
	The Effect of Gamma Radiation on the Dissolution of High-Level Waste Glass in Boom Clay
	Monte Carlo Modeling of Glass Dissolution: Comparison with Experiments

 

Ceramic Wasteforms
	Nd and Ce-doped Ceramic Glass Composites: Chemical Durability Under Aqueous Leaching Conditions
	Structural Effect of Pu Substitutions on the Zr-Site in Zirconolite
	Durability Of Zirconolite In Hydrothermal Fluids: Implications For Nuclear Waste Disposal
	Melted Synthetic Zirconolite-Based Matrices: Effect of Cooling Rate and Heat Treatment on Ceramic Microstructure and Chemical Durability
	Surface Alteration of Nd-Bearing Zirconolite Following Hydrothermal Treatment
	Effects Of Cesium, Iodine And Strontium Ion Implantation On The Microstructure Of Cubic Zirconia
	Feasibility Limits in Using Cerium as a Surrogate for Plutonium Incorporation in Zircon, Zirconia and Pyrochlore
	Synthesis and Study of 239Pu-Doped Ceramics Based on Zircon, (Zr,Pu)Sio4, and Hafnon, (Hf,Pu)SiO4
	Effect of Synthesis Conditions on Phase Composition of Pyrochlore-Brannerite Ceramics
	Durabilities Of Pyrochlore-Rich Titanate Ceramics Designed For Immobilization Of Surplus Plutonium
	Pyrochlore-Rich Synroc as a Host for Immobilization of Actinides
	Dissolution Of Synthetic Brannerite At 90°C
	Emanation Thermal Analysis Study of Metamict Brannerite
	Phase and Chemical Stability of Murataite Containing Uranium, Plutonium, and Rare Earths
	Perovskite Ceramics from Mechanically Activated Batches for Immobilization of Rare Earth­Actinide Fraction of HLW
	Measured Displacement Energies of Oxygen Ions in Zirconolite and Rutile
	Aqueous Dissolution of Rb-Bearing Hollandite and Synroc-C at 90°C

 

Spent Fuel
	Leaching Behavior and a-Decay Damage Accumulation of UO2 Containing Short-Lived Actinides
	Effect Of Spent Fuel Burnup And Composition On Alteration Of The U(Pu)O2 Matrix
	The Effect Of Hydrogen Peroxide Concentration On The Oxidative Dissolution Of Unirradiated Uranium Dioxide
	Congruent And Incongruent Radionuclide Release During Matrix Dissolution of Partly Oxidized High Burnup Spent Fuel
	On Metal Aggregates in Spent Fuel, Synthesis and Leaching of a Mo-Ru-Pd-Rh Alloy
	Influence of Container Base Material (Fe) on SIMFUEL Leaching Behavior
	Long-Term Dissolution Behavior of Spent Fuel in Compacted Bentonite and Synthetic Granitic Groundwater
	Release of Radiotoxic Elements from High Burn-Up UO2 and MOX Fuel in a Repository
	Release of Radionuclides from Spent Fuel Under Repository Conditions: Mathematical Modeling and Preliminary Results
	A New Approach to the RN Source Term for Spent Nuclear Fuel Under Geological Disposal Conditions

 

Canisters
	Mechanical Properties of Oxides Formed by Anaerobic Corrosion of Steel
	Electrochemical Measurements During the Anaerobic Corrosion of Steel
	Influence Of Oxygen Concentration And Alkalinity On The Hydrogen Gas Generation By Corrosion Of Carbon Steel
	Corrosion Processes Affecting the Performance of Alloy 22 as a High-Level Radioactive Waste Container Material
	Evaluation of the Possible Susceptibility of Titanium Grade 7 to Hydrogen Embrittlement in a Geologic Repository Environment
	Study of Consequences of Secondary Water Radiolysis Within and Surrounding a Defective Canister
	The Influence of Ligands and Precipitates on the Release of Nuclides From the Near Field Under Natural Repository Conditions

 

Engineered Barriers
	Material For The Engineered Barrier System Under Development For The LlW Repository In Italy
	GMT -- A Large Scale In Situ Test of the Gas Migration Properties of Engineered Barriers
	Coupled Thermo-Hydro-Geochemical Models of Engineered Barrier Systems: The FEBEX Project
	Pore Water Chemistry of the FEBEX Bentonite
	Ion Exchange Behavior of the FEBEX Bentonite -- 1. Na/K, Na/Mg and Na/Ca Experimental Exchange Isotherms
	Ion Exchange Behavior of the FEBEX Bentonite -- 2. Batch Experiments and Geochemical Modeling
	The Effect of Pore Structural Factors on Diffusion in Compacted Sodium Bentonite
	Mass Transport of Multicomponents Solute of Bentonite Clay
	Diffusion Behavior of Ca2+ Ions in Compacted Na-Montmorillonite
	Experimental Indications Of Effects Of Surface Deprotonation On Na-Bentonite Porewater Chemistry in a Geological Repository
	The Effect of the Excavation Damaged Zone Adjacent to the Walls of Deposition Holes on the Migration of Radionuclides

 

Microbiology and Thermodynamics
	Laboratory Examination Of Microbial Perturbations in a Granitic Environment
	Integrating Microbiology Into the Drigg Post-Closure Radiological Safety Assessment
	A Study on Conditions for Microbial Transport Through Compacted Buffer Material
	Effects of Lichens on Uranium Migration
	Enthalpies of Formation of Gd2(Ti2-xZrx)O7 Pyrochlores

 

Repository Studies
	Key Aspects of the H12 Safety Case
	The National Radioactive Waste Repository Project
	Moving HLW-EBS Concepts into the 21st Century
	The Maralinga Rehabilitation Project
	SR 97: Post-Closure Safety For A KBS 3 Deep Repository For Spent Nuclear Fuel -- Overview
	SR-97: Canister Performance under Normal Disposal Conditions
	SR 97: Hydromechanical Evolution In A Defective Canister
	SR 97: Spent Fuel Alteration/Dissolution And The Influence Of Near Field Hydrogen
	Radionuclide Transport Calculations in the Safety Assessment SR 97
	Using Results from Tru Experiments for WIPP to Determine Model Development and Needed Experimental Programs
	Modeling of Near Field Actinide Concentrations in Radioactive Waste Repositories in Salt Formations: Effect of Buffer Materials
	Status Of The Pangea International Repository Feasibility Studies
	Approaches to Comparative Risk Assessments of National and International Radioactive Waste Disposal Options
	Thermal Considerations in a Very Deep Borehole Nuclear Waste Repository for Synroc
	Progress in the Geomicrobiology of Radioactive Waste Disposal
	Simulation of the Waste Glass Behavior in a Loamy Soil of the Wet Repository Site
	Repository Design Optimization for Long-Lived ILW
	Effects of Confining Pressure on Gas and Water Permeabilities of Rocks
	Retrievability: Rationale, Measures, Impacts
	Determination of the Flow-Wetted Surface in Fractured Media
	Scenarios Selection for a Simple Concept Landfill
	Radiation Effects on Materials in the Near-Field of a Nuclear Waste Repository
	Grimsel 2000 -- Status of International Projects at the Grimsel Test Site (GTS)
	Development and Analysis of Scenarios for a Permanent Repository for Radioactive Wastes in Salt Rock
	Application of Supplementary Safety Indicators for H12 Performance Assessment

 

Natural Systems
	An Overview of the Crystal Chemistry, Durability and Radiation Damage Effects of Natural Pyrochlore
	Alteration of Uranium-Rich Microlite
	Alteration Features in Natural Zirconolite from Carbonatites
	Galena Crystallization and the Origin of Sulfur in the Oklo and Bangombé Natural Reactors: Effects of a ca. 900 Ma Thermal Event
	Isotropic Fractionation of U in Rocks Reflecting Redox Conditions Around a Groundwater Flow Route
	Field and Laboratory Examination of Uranium Microcrystallization and its Role in Uranium Transport
	Geochemistry of Hydrothermal Veins Containing Zirconolite And Betafite At Adamello, Italy
	Partitioning of Actinides, Rare Earth Elements, and Other Trace Elements In Titanium-Rich Veins From Adamello, Italy
	Surveying for Migration Pathways in the Granitic Rock Using Nuclear Track Detectors, Autoradiography and Digital Imaging Analysis as an Aid To Construct the Basis for Heterogeneous Diffusion Modeling

 

Solubility, Transport Modeling and Migration
	Remedial Action for Radioactive Waste Rock Piles in China
	Influence of Colloids in Experimental Solubility Studies of Ni in Natural and Synthetic Aqueous Media
	Insights to Repository Performance Through Study of a Nuclear Test Site
	Building Confidence in Radionuclide Transport Models for Fractured Rock: The Nagra/JNC Radionuclide Retardation Programme
	Revisiting the Advection-Dispersion Model -- Testing an Alternative
	Discussion on the Use of Matrix Diffusion Model After a Multidisciplinary Study of a Granitic Boulder Sample
	Brownian Simulation of Matrix Diffusion
	Surface Conductivity and Diffusion Models -- Comparison and Evaluation
	Experimental Study and Modeling of the Radium Sorption Onto Goethite
	On the Hydrolysis of Tetravalent Metal Ions
	Use of Multi-Dimensional Sorption Data-Sets to Constrain Models of Radionuclide-Solid Interactions
	Studies of Sorption of Th and Np on UO2 and TiO2
	Radionuclide Movement During Unsteady, Unsaturated Soil Water Flow
	Migration of Cs-137 and Co-60 in Drill Samples from the Australian Arid Zone
	Evidence of Heterogeneous Matrix Diffusion in Fractured Crystalline Rock in Laboratory Migration Experiments
	The Solubility of Metallic Selenium Under Anoxic Conditions
	Experimental Study of Nickel Solubility in Sulfidic Groundwater Under Anoxic Conditions
	Isolation and Microscopic Characterization of Nuclear Fuel Particles from Two Contaminated Soils of Chernobyl.
	Migration Mechanisms of Americium(III) Through Soil Layers
	Tritium and Iodite Diffision Through Opalinus Clay
	Matrix Diffusion Measurements -- Through Diffusion Versus Electrical Conductivity Measurements
	Formation Factor Determinations by In Situ Resistivity Logging
	Sorption Behavior of Radium and Actinium on Soils
	Diffusion and Adsorption in Porous Silica Considered as a Reference Material for Crystalline Rock

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