Scientific Basis for Nuclear Waste Management

Front Matter....Pages i-xix
Remarks About Department of Energy Policy on High-Level Nuclear Waste Management....Pages 1-4
Regulation of Geologic Repositories for the Disposal of High-Level Radioactive Wastes....Pages 5-19
Survey of High-Level Radioactive Waste Forms and Their Role in Waste Management....Pages 21-30
Radioactive Waste Disposal in Geological Formations: Research Activities of the Commission of the European Communities....Pages 31-37
Development of Solid Radionuclide Waste Forms in the United States....Pages 39-51
The Environmental Effects Associated with the Transportation of Radioactive Material....Pages 53-60
The Perspective of Waste Isolation Research Issues and Assessment of Consequences for Radionuclide Release....Pages 61-68
Status Report on Studies to Assess the Feasibility of Storing Nuclear Waste in Columbia Plateau Basalts....Pages 69-76
General Criteria for Radioactive Waste Disposal....Pages 77-84
Characterization of Weathered Glass by Analyzing Ancient Artifacts....Pages 85-92
An Investigation on the Valency State of Molybdenum in Glasses with and without Fission Products....Pages 93-102
Resistance of High-Level Waste Materials to Dissolution in Aqueous Media....Pages 103-108
Chemical Stability of a Phosphate Glass under Hydrothermal Conditions....Pages 109-116
The Behavior of Actinides in α- Doped Glasses as Regards to the Long Term Disposal of High Level Radioactive Materials....Pages 117-125
Atomic Displacements and Radiation Damage in Glasses Incorporating HLW....Pages 127-133
A Microscopic Approach for the Simulation of Radioactive Waste Storage in Glass....Pages 135-140
Devitrification of Nuclear Waste Glasses....Pages 141-146
High-Level Waste Vitrification Product Characterization....Pages 147-154
Long-Term Extrapolation of Laboratory Glass Leaching Data for the Prediction of Fission Product Release Under Actual Groundwater Conditions....Pages 155-166
Leaching Characteristics of Actinides from Simulated Reactor Waste, Part 2....Pages 167-173
Statistically Designed Study of a Nuclear Waste Glass System....Pages 175-181
Dissolution of Borosilicate Glasses under Repository Conditions of Pressure and Temperature....Pages 183-190
Mechanism for Elevated Temperature Leaching....Pages 191-198
Brine Chemistry Effects on the Durability of a Simulated Nuclear Waste Glass....Pages 199-206
Hydrothermal Interaction of Simulated Nuclear Waste Glass in the Presence of Basalts....Pages 207-214
Vitrification of High-Level Alumina Nuclear Waste....Pages 215-222
Improved Glass Compositions for Immobilization of SRP Waste....Pages 223-229
Multibarrier Storage of Savannah River Plant Waste....Pages 231-238
Temperature Dependence for Hydrothermal Reactions of Waste Glasses and Ceramics....Pages 239-248
Microstructural Characterization of Glass and Ceramic Simulated Waste Forms....Pages 249-254
Alternative Waste Forms — A Comparative Study....Pages 255-264
Immobilization of U.S. Defense Nuclear Wastes Using the Synroc Process....Pages 265-272
The Effects of Radiation Damage on Synroc....Pages 273-280
Uranium and Thorium Minerals: Natural Analogues for Radioactive Waste Forms....Pages 281-288
Monazite and Other Lanthanide Orthophosphates as Alternate Actinide Waste Forms....Pages 289-296
Crystal Chemistry and Phase Relations in the Synthetic Minerals of Ceramic Waste Forms: I. Fluorite and Monazite Structure Phases....Pages 297-306
Characterization of Impact Fracture of Brittle Solid Waste Forms....Pages 307-314
Development and Characterization of Cermet Forms for Radioactive Waste....Pages 315-322
Long-Term Leaching of Irradiated Spent Fuel....Pages 323-334
Leaching of Irradiated Candu UO 2 Fuel....Pages 335-342
Low Temperature Ceramic Waste Form: Characterization of Monazite Cement Composites....Pages 343-349
Structure and Stability of Incinerated α-Waste Products....Pages 351-359
Krypton-85 Storage in Solid Matrices....Pages 361-368
Technical Feasibility of Krypton-85 Storage in Sodalite....Pages 369-376
Corrosion-Resistant Metallic Canisters for Nuclear Waste Isolation....Pages 377-384
Corrosion of Materials in a Clay Environment....Pages 385-393
Canister Compatibility with Carlsbad Salt....Pages 395-402
The Backfill as an Engineered Barrier for Nuclear Waste Management....Pages 403-410
Superoverpack: Tailor-Made Mixtures of Zeolites and Clays....Pages 411-418
Solution Interaction of Nuclear Waste Anions with Selected Geological Materials....Pages 419-426
Clay Minerals Suitable for Overpack in Waste Repositories: Evidence From Uranium Deposits....Pages 427-435
Comparison of Tailored Cement Formulations for Borehole Plugging in Crystalline Silicate Rocks and Evaporite Mineral Sequences....Pages 437-444
Clay Mineral-Brine Interactions During Evaporite Diagenesis: Lanthanide Distribution in WIPP Samples....Pages 445-452
Thermal Gradient Migration of Fluid Inclusions in Single Crystals of Salt from the Waste Isolation Pilot Plant Site (WIPP)....Pages 453-464
The Application of the Physicochemical Properties of Boiling Bitterns to the Interpretation of Brine Migration Experiments Related to Salt Repositories....Pages 465-470
Modeling of Brine Migration in Halite....Pages 471-478
Long-Term Stability of Evaporite Minerals: Geochronological Evidence....Pages 479-486
Tracer Tests Performed in the Field for WIPP in Southeastern New Mexico....Pages 487-489
In Situ Experiments to Support Development of the Waste Isolation Pilot Plant (WIPP)....Pages 491-498
Shale Rocks as Nuclear Waste Repositories: Hydrothermal Reactions with Glass, Ceramic and Spent Fuel Waste Forms....Pages 499-506
Hydrogeologic Characteristics of Fractured Rocks for Waste Isolation — The Stripa Experience....Pages 507-518
The Role of Large-Scale Permeability Measurements in Fractured Rock and their Application at Stripa....Pages 519-526
Characterization of Discontinuities in the Stripa Granite....Pages 527-534
Rock Instrumentation Problems Experienced during in Situ Heater Tests....Pages 535-542
Geochemistry, Origin and Age of Groundwaters in the Stripa (Sweden) Test Mine....Pages 543-552
Recent Studies on Radiation Damage Formation in Synthetic NaCl and Natural Rock Salt for Radioactive Waste Disposal Applications....Pages 553-560
Physico-Chemical Processes in Rock Salt under Irradiation....Pages 561-567
Gas Generation from Transuranic Waste Degradation....Pages 569-575
The Reaction of Hydrogen and Oxygen in the Presence of Concretes Incorporating Simulated Radioactive Waste....Pages 577-584
Radiolytic Gas Generation in Concrete Made with Incinerator Ash Containing Transuranium Nuclides....Pages 585-592
Influence of Ionizing Irradiation on the Properties of Alumosilicate Mineral Rock Repositories of Radioactive Wastes....Pages 593-599
 99 Tc, Pb and Ru Migration Around the Oklo Natural Fission Reactors....Pages 601-608
Parameters Affecting Radionuclide Migration in Geologic Media....Pages 609-616
Radionuclide Transport in a Dolomite Aquifer....Pages 617-624
Chemical Reactions in the Bedrock-Groundwater System of Importance for the Sorption of Actinides....Pages 625-631
Interaction of Radionuclides with Geomedia from the Nevada Test Site....Pages 633-640
Radionuclide Sorption Studies on Abyssal Red Clays....Pages 641-646
Measurement of Penetration Depths of Plutonium and Americium in Sediment from the Ocean Floor....Pages 647-654
The Radiolytic Oxidation and Reduction of Plutonium....Pages 655-664
Transport through Deep Aquifers of Transuranic Nuclides Leached from Vitrified High-Level Wastes....Pages 665-671
Possible Retention of Iodine in the Ground....Pages 673-680
Asphalt Emulsion Sealing of Uranium Mill Tailings....Pages 681-688
Waste Isolation Performance Assessment — A Status Report....Pages 689-702
Ion Migration in Ocean Sediments: Subseafloor Radioactive Waste Disposal....Pages 703-710
Radioactive Waste Disposal into a Plastic Clay Formation: Probabilistic Assessment of the Geological Containment....Pages 711-720
Finite Medium Green’s Function Solutions to Nuclide Transport in Porous Material....Pages 721-728
Preliminary Rate Expressions for Analysis of Radionuclide Migration Resulting from Fluid Flow Through Jointed Media....Pages 729-738
The Complex Relationship between Groundwater Velocity and Concentration of Radioactive Contaminants....Pages 739-745
Kinetic Effects on Radionuclide Transport of Groundwater....Pages 747-752
The Effect of Variations in Parameter Values on the Predicted Radiological Consequences of Geologic Disposal of High-Level Waste....Pages 753-762
Sensitivity Studies of the Swift Radionuclide Transport Model....Pages 763-770
Development of Scenarios for the Long-Term Release of Radionuclides from the Proposed Waste Isolation Pilot Plant in Southeastern New Mexico....Pages 771-778
A Stochastic Model of Radionuclide Migration from Natural and Engineered Repositories....Pages 779-785
An Application of Geometric Probability to the Existence of Faults in Anisotropic Media....Pages 787-794
Geologic Waste Disposal and a Model for the Surface Movement of Radionuclides....Pages 795-802
Regional Thermohydrological Effects of an Underground Repository for Nuclear Wastes in Hard Rock....Pages 803-810
Environmental Effects from Disposal of Defense High-Level Radioactive Wastes in a Generic Geologic Repository....Pages 811-816
Far Field Thermal Calculations for the WIPP Site in Southeastern New Mexico (SENM)....Pages 817-824
Temperatures Generated by Underground Storage of Defense Waste Canisters....Pages 825-832
Calculated Hydrogeologic Pressures and Temperatures Resulting from Radioactive Waste in the Eleana Argillite....Pages 833-840
A Systematic Approach for Assessment of Alternative Nuclear Waste Management Strategies....Pages 841-848
A Review of the Environmental Impact of Mining and Milling of Uranium Ores....Pages 849-857
Processing of High-Temperature Simulated Waste Glass in a Continuous Ceramic Melter....Pages 859-866
Fixation of Medium-Level Wastes in Titanates and Zeolites:Progress Towards a System for Transfer of Nuclear Reactor Activities from Spent Organic to Inorganic Ion Exchangers....Pages 867-874
Development of an Ion-Exchange Process for Removing Cesium from High-Level Radioactive Liquid Wastes....Pages 875-884
Actinide Separation from HLLW....Pages 885-892
Methods For Separating Actinides From Reprocessing And Refabrication Plant Wastes....Pages 893-900
Ruthenium Volatility Behaviour during HLLW-Vitrification in a Liquid-Fed Ceramic Waste Melter....Pages 901-910
Effect of Denitration on Ruthenium Volatilization....Pages 911-917
Advances in the Fluorocarbon Process for Decontamination of Nuclear Facility Off-Gases....Pages 919-926
Back Matter....Pages 927-936