Scientific Basis for Nuclear Waste Management, Softcover reprint of the original 1st ed. 1981
Volume 3

The third International Symposium on the Scientific Basis for Nuclear Waste Management was held in Boston, Massachusetts, on November 17-20, 1980, as part of the Annual Meeting of the Materials Research Society. The purpose of this Symposium was to provide an interdisciplinary forum for the discussion of scientific research dealing with all levels and types of radioactive wastes and their management. Since its inception in 1978, this annual Symposium has provided a unique opportunity for scientists of widely differing backgrounds to share in such discussions. The proceedings of the first two meetings were published as Volumes 1 and 2 in this series. The fourth Symposium is scheduled to be held in the autumn of 1981. The efforts of many people went into making this meeting a success. The scope of the 1980 Symposium was guided by the follow­ ing Steering Committee: K. J. Notz (Chairman), Oak Ridge National Laboratory, USA G. H. Daly, Department of Energy, USA D. E. Ferguson, Oak Ridge National Laboratory, USA R. H. Flowers, Atomic Energy Research Establishment, UK F. Girardi, Ispra Establishment, Italy T. Ishihara, Radioactive Waste Management Center, Japan R. W. Lynch, Sandia Laboratories, USA S. A. Mayman, Atomic Energy of Canada Ltd. , Canada G. J. McCarthy, North Dakota State University, USA E. Merz, Kernforschunganlage Jillich, FRG L. Nilsson, KBS Project, Sweden D. M. Rohrer, Nuclear Regulatory Commission, USA R. Roy, Pennsylvania State University, USA T. "E. Scott, Ames Laboratory, USA C.

Repository Characterization.- Development of Reference Conditions for Geologic Repositories for Nuclear Waste in the USA.- Basalt Waste Isolation Project Data Package for Reference Physicochemical Conditions.- Evaluation of Product Specifications with a Safety Analysis for a Disposal Mine.- Predicting the Reaction State of Brines in Proposed Regions of Nuclear Waste Isolation.- Laboratory Investigations of Water Content within Rock Salt and Its Behavior in a Temperature Field of Disposed High-Level Waste.- Thermal Conductivity of Selected Repository Minerals.- Phase Chemistry of the Umtanum Basalt, a Reference Repository Host in the Columbia Plateau.- Geoscientific Evaluation of Radioactive Waste Isolation in Japan.- High-Level Waste Forms.- Assessment and Head end Processing.- Preliminary Evaluation of Alternative forms of Immobilization of Hanford High-Level Wastes.- Development of an Improved Ion-Exchange Process for Removing Cesium and Strontium from High-Level Radioactive Liquid Wastes.- Vitreous Materials.- A Small-Scale Integrated Demonstration of High-Level Radioactive Waste Processing and Vitrification Using Actual SRP Waste.- Advanced Method for Making Vitreous Waste Forms.- An ESCA Investigation of Molybdenum Containing Silicate and Phosphate Glasses.- Structural and Redox Properties of Uranium in Ca-Mg-Al-Silicate Glasses.- Stable Product Low Leach Glasses.- Crystalline Materials.- Titanate Waste forms for High Level Waste — an Evaluation of Materials and Processes.- The Stability of Perovskite and Sphene in the Presence of Backfill and Repository Materials: A General Approach.- Tailored Ceramic Nuclear Waste Forms: Preparation and Characterization.- Recent Progress on Synroc Development.- Matrix-Encapsulated Waste forms: Application to Ideolized Systems, Commercial and SRP/INEL Wastes, Hydrated Radiophases, and Encapsulant Phases.- Phase Equilibria Leaching Characteristics and Ceramic Processing of Synroc D for U.S. Defense Wastes.- Sol-Gel Technology Applied to Crystalline Ceramic Nuclear Waste Forms.- The Characterization of Nuclear Waste forms by EPR Spectroscopy.- Valence States of Actinides in Synthetic Monazites.- Crystal Chemistry and Phase Relations in the Synthetic Minerals of Ceramic Waste Forms. II. Studies of Uranium-Containing Monazites.- Non-High-Level Waste.- Characterization of Iron-Enriched Synthetic Basalt for Transuranic Containment.- Treatment of Cladding Hulls by the Hipow Process.- Bituminization of Low-Level Liquid Waste.- Studies on Sintered Titanates and Zeolites as Hosts for Medium Level Radioactive Waste.- Diffusion Of Cs in Concrete.- Precipitation of Radiostrontium in Soil.- Loading and Leakage of Krypton Immobilized in Zeolites and Glass.- The Lasl Experimental Engineered Waste Burial Facility: Design Considerations and Preliminary Plan.- Melting Process to Condition Decladding Hulls Generated by the Reprocessing of LWR and FBR Spent Fuels.- Natural Analogues.- Alkali and Alkaline Earth Element Studies at Oklo.- Durability of Rhyolitic Obsidian Glass Inferred from Hydration Dating Research.- Backfill Barriers: The Use of Engineered Barriers Based on Geologic Materials to Assure Isolation of Radioactive Wastes in a Repository.- Natural Analogues for Crystaline Radioactive Waste Forms, Part II; Non-Actinide Phases.- Geochemical Study of a Lamprophyre Dike Near the Wipp Site.- Nuclear Waste Glasses and Volcanic Glasses: a Comparison of Their Stabilities.- Leach Studies.- Surface Analysis—Its Uses and Abuses in Waste form Evaluation.- Are Solubility Limits of Importance to Leaching?.- Leach and Corrosion Tests Under Normal and Accident Conditions on Cement Products from Simulated Intermediate Level Evaporator Concentrates.- Standard Leach Tests for Nuclear Waste Materials.- Time and Temperature Dependence of the Leaching of a Simulated High-Level Waste Glass.- The Mechanisms for Hydrothermal Leaching of Glass and Glass-Ceramic Nuclear Waste Forms.- The Influence of Surface Processes in Waste form Leaching.- Probable Leaching Mechanisms for UO2 and Spent Fuel.- Stability of Pollucite in Hydrothermal Fluids.- XPS and Ion Beam Scattering Studies of Leaching in Simulated Waste Glass Containing Uranium.- Radiation Effects.- Spontaneous Fragmentation of an Alpha-Active Ceramic — A Mechanism for Dispersion of Solid Waste?.- Experimental Study of Structural Damage in Crystalline Nuclear Waste Phases from Fission Fragment Irradiation.- Metamictization by Heavy Ion Bombardment of ?-Quartz, Zircon, Monazite and Nitride Structures.- Experimental Evaluation of Changes in Properties of Natural Minerals under Irradiation.- Radiation Hardening of Rocksalt.- Radiation Effects in Crystalline High-Level Nuclear Waste Solids.- Radiation Damage Effects on the Leach Resistance oF Glasses and Minerals: Implications for Radioactive Waste Storage.- Radionuclide Migration.- Cesium Migration Through Solid Cores of Magenta Dolomite.- Sorption Studies of H14CO3- on Some Geologic Media and Concrete.- Some Difficulties in Interpreting In-Situ Tracer Tests.- Radionuclide Transport and Retardation in Tuff.- Temperature and pH Effects on Sorption Properties of Subseabed Clay.- SrCl2 Solubility in Complex Brines.- Geologic Stability of Monazite and Its Bearing on Immobilization of Actinide Wastes.- Engineered Barriers.- Development of Structural Engineered Barriers for the Long-Term Containment of Nuclear Waste.- Evaluation of Metallic Materials for Use in Engineered Barrier Systems.- Evaluation of Ceramic and Polymeric Materials for Use in Engineered Barrier Systems.- Technical Barriers Against a Contact of Ground Water with Disposed Radioactive Waste.- Composite Backfill Materials for Radioactive Waste Isolation by Deep Burial in Salt.- Highly Compacted Bentonite — A Self-Healing Substance for Nuclear Waste Isolation.- The Bell Canyon Test and Results.- Performance Assessment.- Modelling of Rock Masses for Radioactive Waste Repositories in Hard Rock.- A Combined Fracture/Porous Media Model for Contaminant Transport of Radioactive Ions.- Sensitivity of Calculated Pore-Fluid Pressure Repository Fracture Geometry.- An Evaluation of the Ability to Predict Radionuclide Transport in Groundwater Flow Systems.- An Analysis on the Use of Engineered Barriers for Geologic Isolation of Spent Fuel.- Thermal Analysis for a Spent Reactor Fuel Storage Test in Granite.- Author Index.