Ebook: Scientific Basis for Nuclear Waste Management: Volume 1 Proceedings of the Symposium on “Science Underlying Radioactive Waste Management,” Materials Research Society Annual Meeting, Boston, Massachusetts, November 28–December 1, 1978

During late 1978, a symposium entitled "Science Underlying Radioactive Waste Management" was one component of the Annual Meet­ ing of the Materials Research Society held in Boston, Massachusetts. The purpose of this Symposium was to bring together for the first time the entire range of sciences that form the basis for the treatment, solidification and isolation of radioactive wastes. Some 79 papers were presented to an international audience of over 300. The Symposium was such an impressive success that another will be held at the 1979 Annual Meeting of the Materials Research Society. The proceedings of the forthcoming symposium will also be published and it is for this reason that the present volume has been desig­ nated Volume 1. The scope of the Symposium was defined by the following steer­ ing committee: Rustum Roy, The Pennsylvania State University (Chairman) Richard S. Claassen, Sandia Laboratories Don Ferguson, Oak Ridge National Laboratory Victor I. Spitsyn, U.S.S.R. Academy of Sciences, Moscow David B. Stewart, United States Geological Survey Torbjorn Westermark, Royal Institute of Technology, Stockholm. The program was organized by the following committee: Gregory J. McCarthy, The Pennsylvania State University (Cha- man) Harry C. Burkholder, Battelle Memorial Institute Arnold M. Friedman~ Argonne National Laboratory Werner Lutze, Hahn-Meitner Institut, Berlin John G. Moore, Oak Ridge National Laboratory Robert W. Potter, II, United States Geological Survey Richard L. Schwoebe1, Sandia Laboratories Roger W. Staehle, Ohio State University.

---

---

Content:
Front Matter....Pages i-xviii
Science Underlying Radioactive Waste Management: Status and Needs....Pages 1-20
Techniques for High Level Waste Solidification in Europe....Pages 21-29
Development of Glass Compositions for Immobilization of Savannah River Plant Waste....Pages 31-35
Preparation and Characterization of an Improved High Level Radioactive Waste (HAW) Borosilicate Glass....Pages 37-42
Vitrification of High Sodium-Aluminum Wastes: Composition Ranges and Properties....Pages 43-50
Non-Radioactive Operation Experience with a Joule Heated Ceramic Melter for Vitrification of High-Level Liquid Waste....Pages 51-56
Natural Glasses: Analogues for Radioactive Waste Forms....Pages 57-68
Characterization of Glass and Glass Ceramic Nuclear Waste Forms....Pages 69-81
Microstructural Characterization of Solidified Simulated Reactor Wasteforms....Pages 83-96
Bonding of Metal Oxides in Sodium Silicate Glass....Pages 97-107
Helium Formation from ?-Decay and its Significance for Radioactive Waste Glasses....Pages 109-115
Thermal, Chemical and Radiation Stability of Vitreous Radioactive Wastes....Pages 117-121
Chemistry of Nuclear Waste Glass Reactions: Problems and Potential of Prediction....Pages 123-129
Characterization of Leached Surface Layers on Simulated High-Level Waste Glasses by Sputter-Induced Optical Emission....Pages 131-139
Leaching Characteristics of Actinides from Simulated Reactor Waste Glass....Pages 141-147
Leach Rate Characterization of Solid Radioactive Waste Forms....Pages 149-155
Long-Term Elevated Temperature Leaching of Solid Waste Forms....Pages 157-160
Calculations of Radioactivity Release Due to Leaching of Vitrified High Level Waste....Pages 161-168
Development of Multibarrier Nuclear Waste Forms....Pages 169-180
Metal Encapsulation of Ceramic Nuclear Waste....Pages 181-189
Cermets for High Level Waste Containment....Pages 191-193
Clay-Phosphate Ceramics and Vitromets: Alternatives to Monolithic High Level Waste Glass Products....Pages 195-200
Synthetic Rutile Microencapsulation: A Radioactive Waste Solidification System Resulting in an Extremely Stable Product....Pages 201-205
Hot Isostatic Pressing for the Consolidation and Containment of Radioactive Waste....Pages 207-210
Characterization of a Titanate Based Ceramic for High Level Nuclear Waste Solidification....Pages 211-217
Raman Spectra of Cesium Aluminosilicate Waste Forms....Pages 219-225
Investigations of the Volatility of Cesium from Aluminosilicates by Mass Spectrometry....Pages 227-229
Pollucite and its Alteration in Geological Occurrences and in Deep-Burial Radioactive Waste Disposal....Pages 231-236
The Scientific Basis For, and Experience With, Underground Storage of Liquid Radioactive Wastes in the USSR....Pages 237-248
Influence of Radiation on the System Liquid Radioactive Wastes-Geologic Formation....Pages 249-255
Waste Disposal by Shale Fracturing at ORNL....Pages 257-260
The Rock-Melt Approach to Nuclear Waste Disposal in Geological Media....Pages 261-264
Interaction of a Glass-Based Nuclear Waste Simulant and Natural Rock....Pages 265-270
Corrosion Resistance of Canisters for Final Disposal of Spent Nuclear Fuel....Pages 271-281
Corrosion Considerations for Nuclear Waste Isolation Canisters....Pages 283-287
Preliminary Corrosion Test of a Glass-Ceramic Candidate for a Nuclear Waste Canister....Pages 289-296
Application of Physical Chemistry of Fluids in Rock Salt at Elevated Temperature and Presssure to Repositories for Radioactive Waste....Pages 297-311
Application of Studies of Fluid Inclusions in Permian Salado Salt, New Mexico, to Problems of Siting the Waste Isolation Pilot Plant....Pages 313-321
P-T-X Relations of Anhydrite and Brine and their Implications for the Suitability of Anhydrite as a Nuclear Waste Repository Medium....Pages 323-328
Hydrothermal Reactivity of Simulated Nuclear Waste Forms and Water-Catalysed Waste-Rock Interactions....Pages 329-340
Hydrothermal Glass Reactions in Salt Brine....Pages 341-344
Long Term Geochemical Interactions of High Active Waste with Crystalline Rock Repository Media....Pages 345-347
Radiation Damage Studies on Natural and Synthetic Rock Salt for Waste Disposal Applications....Pages 349-354
Thermodynamic Considerations Underlying the Migration of Radionuclides in Geomedia: Oklo and Other Examples....Pages 355-366
Measurements of Parameters Essential to Predicting Nuclide Migration....Pages 367-377
Interaction of Waste Radionuclides with Geomedia: Program Approach and Progress....Pages 379-394
Radionuclide Migration Studies Associated with the WIPP Site in Southern New Mexico....Pages 395-398
Migration of Cesium in Dolomite from the Rustler Formation in the Los Medanos Area in Southeastern New Mexico....Pages 399-402
Nuclide Transport by Groundwater in Swedish Bedrock....Pages 403-410
Analysis of Some Tracer Runs in Granite Rock Using a Fissure Model....Pages 411-415
Chemistry of Tc-99 and Np-237 in Contact with Unweathered Igneous Rocks....Pages 417-418
Interactions of Simulated Waste Radionuclides and Rocks....Pages 419-422
Sorption and Migration of Radionuclides in Geologic Media....Pages 423-426
Analysis of Pu-Release Consequences on the Environmental Geochemistry....Pages 427-434
Variables Affecting Sorption and Transport of Radionuclides in Hanford Subsoils....Pages 435-438
The Effect of Retardation Factors on Radionuclide Migration....Pages 439-442
Studies of Concrete as a Host for Savannah River Plant Radioactive Waste....Pages 443-452
The Disposal of Iodine-129....Pages 453-459
Role of Admixtures in Preparing Dense Cements for Radioactive Waste Isolation....Pages 461-466
Immobilization of Strontium and Cesium in Intermediate-Level Liquid Wastes by Solidification in Cements....Pages 467-470
Permeability Measurements on Cementitious Materials for Nuclear Waste Isolation....Pages 471-478
The Development of Process and Storage Materials Suitable for Krypton-85 Waste Management....Pages 479-485
Confinement of Volatilized Ruthenium Oxides....Pages 487-490
Technical Challenges in the Immobilization of Hanford Defense Waste....Pages 491-494
Physicochemical Characterization of Solidification Agents Used and Products Formed with Radioactive Wastes at LWR Nuclear Power Plants....Pages 495-498
Low-Level Solidified Waste Characterization: The Scientific Basis for Physical and Chemical Testing....Pages 499-500
An Analysis of the Geological Stability of a Hypothetical Radioactive Waste Repository in a Bedded Salt Formation....Pages 501-511
Preliminary Safety Assessment of the WIPP Facility....Pages 513-520
Computer Enhanced “Release Scenario” Analysis for a Nuclear Waste Repository....Pages 521-531
Methodology for Estimating Accidental Radioactive Releases in Nuclear Waste Management....Pages 533-539
Release of Radionuclides from High-Level Waste during Transportation Fires....Pages 541-548
Comparison of Some Geologic and Ocean Disposal Concepts Regarding Realistic Modeling that Allows Objective Risk Assessment to be Made....Pages 549-554
Back Matter....Pages 555-563

---

Content:
Front Matter....Pages i-xviii
Science Underlying Radioactive Waste Management: Status and Needs....Pages 1-20
Techniques for High Level Waste Solidification in Europe....Pages 21-29
Development of Glass Compositions for Immobilization of Savannah River Plant Waste....Pages 31-35
Preparation and Characterization of an Improved High Level Radioactive Waste (HAW) Borosilicate Glass....Pages 37-42
Vitrification of High Sodium-Aluminum Wastes: Composition Ranges and Properties....Pages 43-50
Non-Radioactive Operation Experience with a Joule Heated Ceramic Melter for Vitrification of High-Level Liquid Waste....Pages 51-56
Natural Glasses: Analogues for Radioactive Waste Forms....Pages 57-68
Characterization of Glass and Glass Ceramic Nuclear Waste Forms....Pages 69-81
Microstructural Characterization of Solidified Simulated Reactor Wasteforms....Pages 83-96
Bonding of Metal Oxides in Sodium Silicate Glass....Pages 97-107
Helium Formation from ?-Decay and its Significance for Radioactive Waste Glasses....Pages 109-115
Thermal, Chemical and Radiation Stability of Vitreous Radioactive Wastes....Pages 117-121
Chemistry of Nuclear Waste Glass Reactions: Problems and Potential of Prediction....Pages 123-129
Characterization of Leached Surface Layers on Simulated High-Level Waste Glasses by Sputter-Induced Optical Emission....Pages 131-139
Leaching Characteristics of Actinides from Simulated Reactor Waste Glass....Pages 141-147
Leach Rate Characterization of Solid Radioactive Waste Forms....Pages 149-155
Long-Term Elevated Temperature Leaching of Solid Waste Forms....Pages 157-160
Calculations of Radioactivity Release Due to Leaching of Vitrified High Level Waste....Pages 161-168
Development of Multibarrier Nuclear Waste Forms....Pages 169-180
Metal Encapsulation of Ceramic Nuclear Waste....Pages 181-189
Cermets for High Level Waste Containment....Pages 191-193
Clay-Phosphate Ceramics and Vitromets: Alternatives to Monolithic High Level Waste Glass Products....Pages 195-200
Synthetic Rutile Microencapsulation: A Radioactive Waste Solidification System Resulting in an Extremely Stable Product....Pages 201-205
Hot Isostatic Pressing for the Consolidation and Containment of Radioactive Waste....Pages 207-210
Characterization of a Titanate Based Ceramic for High Level Nuclear Waste Solidification....Pages 211-217
Raman Spectra of Cesium Aluminosilicate Waste Forms....Pages 219-225
Investigations of the Volatility of Cesium from Aluminosilicates by Mass Spectrometry....Pages 227-229
Pollucite and its Alteration in Geological Occurrences and in Deep-Burial Radioactive Waste Disposal....Pages 231-236
The Scientific Basis For, and Experience With, Underground Storage of Liquid Radioactive Wastes in the USSR....Pages 237-248
Influence of Radiation on the System Liquid Radioactive Wastes-Geologic Formation....Pages 249-255
Waste Disposal by Shale Fracturing at ORNL....Pages 257-260
The Rock-Melt Approach to Nuclear Waste Disposal in Geological Media....Pages 261-264
Interaction of a Glass-Based Nuclear Waste Simulant and Natural Rock....Pages 265-270
Corrosion Resistance of Canisters for Final Disposal of Spent Nuclear Fuel....Pages 271-281
Corrosion Considerations for Nuclear Waste Isolation Canisters....Pages 283-287
Preliminary Corrosion Test of a Glass-Ceramic Candidate for a Nuclear Waste Canister....Pages 289-296
Application of Physical Chemistry of Fluids in Rock Salt at Elevated Temperature and Presssure to Repositories for Radioactive Waste....Pages 297-311
Application of Studies of Fluid Inclusions in Permian Salado Salt, New Mexico, to Problems of Siting the Waste Isolation Pilot Plant....Pages 313-321
P-T-X Relations of Anhydrite and Brine and their Implications for the Suitability of Anhydrite as a Nuclear Waste Repository Medium....Pages 323-328
Hydrothermal Reactivity of Simulated Nuclear Waste Forms and Water-Catalysed Waste-Rock Interactions....Pages 329-340
Hydrothermal Glass Reactions in Salt Brine....Pages 341-344
Long Term Geochemical Interactions of High Active Waste with Crystalline Rock Repository Media....Pages 345-347
Radiation Damage Studies on Natural and Synthetic Rock Salt for Waste Disposal Applications....Pages 349-354
Thermodynamic Considerations Underlying the Migration of Radionuclides in Geomedia: Oklo and Other Examples....Pages 355-366
Measurements of Parameters Essential to Predicting Nuclide Migration....Pages 367-377
Interaction of Waste Radionuclides with Geomedia: Program Approach and Progress....Pages 379-394
Radionuclide Migration Studies Associated with the WIPP Site in Southern New Mexico....Pages 395-398
Migration of Cesium in Dolomite from the Rustler Formation in the Los Medanos Area in Southeastern New Mexico....Pages 399-402
Nuclide Transport by Groundwater in Swedish Bedrock....Pages 403-410
Analysis of Some Tracer Runs in Granite Rock Using a Fissure Model....Pages 411-415
Chemistry of Tc-99 and Np-237 in Contact with Unweathered Igneous Rocks....Pages 417-418
Interactions of Simulated Waste Radionuclides and Rocks....Pages 419-422
Sorption and Migration of Radionuclides in Geologic Media....Pages 423-426
Analysis of Pu-Release Consequences on the Environmental Geochemistry....Pages 427-434
Variables Affecting Sorption and Transport of Radionuclides in Hanford Subsoils....Pages 435-438
The Effect of Retardation Factors on Radionuclide Migration....Pages 439-442
Studies of Concrete as a Host for Savannah River Plant Radioactive Waste....Pages 443-452
The Disposal of Iodine-129....Pages 453-459
Role of Admixtures in Preparing Dense Cements for Radioactive Waste Isolation....Pages 461-466
Immobilization of Strontium and Cesium in Intermediate-Level Liquid Wastes by Solidification in Cements....Pages 467-470
Permeability Measurements on Cementitious Materials for Nuclear Waste Isolation....Pages 471-478
The Development of Process and Storage Materials Suitable for Krypton-85 Waste Management....Pages 479-485
Confinement of Volatilized Ruthenium Oxides....Pages 487-490
Technical Challenges in the Immobilization of Hanford Defense Waste....Pages 491-494
Physicochemical Characterization of Solidification Agents Used and Products Formed with Radioactive Wastes at LWR Nuclear Power Plants....Pages 495-498
Low-Level Solidified Waste Characterization: The Scientific Basis for Physical and Chemical Testing....Pages 499-500
An Analysis of the Geological Stability of a Hypothetical Radioactive Waste Repository in a Bedded Salt Formation....Pages 501-511
Preliminary Safety Assessment of the WIPP Facility....Pages 513-520
Computer Enhanced “Release Scenario” Analysis for a Nuclear Waste Repository....Pages 521-531
Methodology for Estimating Accidental Radioactive Releases in Nuclear Waste Management....Pages 533-539
Release of Radionuclides from High-Level Waste during Transportation Fires....Pages 541-548
Comparison of Some Geologic and Ocean Disposal Concepts Regarding Realistic Modeling that Allows Objective Risk Assessment to be Made....Pages 549-554
Back Matter....Pages 555-563
....