Glass as a Waste Form and Vitrification Technology: Summary of an International Workshop -- Copyright -- Preface -- Contents -- Executive Summary -- 1 Introduction -- ORGANIZATION OF THE WORKSHOP -- HISTORY -- THE U.S. PROGRAM -- 2 Three "Futures" for Glass -- FUTURE 1: THE ONLY BARRIER TO LONG-TERM RELEASE -- Science -- Technology -- FUTURE 2: AN EFFECTIVE, BUT NOT NECESSARILY THE PRIMARY BARRIER TO LONG-TERM RELEASE -- Science -- Technology -- FUTURE 3: A TOTALLY INEFFECTIVE BARRIER TO LONG-TERM RELEASE -- Science -- Technology -- 3 Special Applications of Glass -- 4 Conclusions -- STATE OF KNOWLEDGE OF THE SCIENCE -- STATE OF PRACTICE OF THE TECHNOLOGY -- FUTURE WASTE FORMS -- References -- Appendix A Biographical Sketches of Steering Committee Members -- Appendix B Workshop Program -- Appendix C List of Workshop Participants -- AUSTRALIA -- BELARUS -- BELGIUM -- CANADA -- CHINA -- CZECH REPUBLIC -- FRANCE -- GERMANY -- JAPAN -- KOREA -- RUSSIA -- SWEDEN -- UNITED KINGDOM -- UNITED STATES -- NRC STAFF -- Appendix D Identification and Summary of Characterization of Materials Potentially Requiring Vitrification -- PREFACE -- 1. Civilian Light-Water-Reactor Spent Fuel -- Genesis -- Description -- 2. DOE-Responsibility Spent Fuels -- Genesis -- Description -- 3. DOE ''Tank'' Wastes -- Genesis -- Description -- 4. Capsules of Separated Radiocesium and Radiostrontium -- Genesis -- Description -- 5. Transuranic Wastes -- Genesis -- Description -- 6. Low-Level Radioactive Wastes -- Genesis -- Description -- 7. Low-Level Mixed Wastes -- Genesis -- Description -- 8. Surplus Plutonium -- Genesis -- Description -- 9. DOE Environmental Restoration Wastes -- Genesis -- Description -- References -- Appendix E Abstracts of Invited Workshop and Poster Presentations -- Vitrification of Radioactive Waste: Past Accomplishments and Future Challenges -- Abstract.

References -- OVERVIEW OF CURRENT DOE PLANS AND ACTIVITIES INVOLVING VITRIFICATION -- IDENTIFICATION AND SUMMARY CHARACTERIZATION OF MATERIALS POTENTIALLYREQUIRING VITRIFICATION -- Hanford Wastes and Glass Composition -- ACCEPTANCE OF WASTE FOR DISPOSAL IN THE POTENTIAL UNTIED STATES REPOSITORY AT YUCCA MOUNTAIN, NEVADA -- INTRODUCTION -- WASTE ACCEPTANCE -- SUMMARY -- A Review of Status of Science of Vitrified Waste Form Development -- Leach Tests and Chemical Durability -- References: -- Status of Vitrification Technologies -- ABSTRACT -- THE CHEMISTRY AND KINETICS OF WASTE GLASS CORROSION -- REFERENCES -- Waste Glass Leaching and Long-Term Modeling -- Waste Glass Leaching and Long-Term Durability -- Corrosion Behavior of Glass: Remaining Scientific Issues -- (1) General glass dissolution phenomena -- (2) Behavior of safety relevant radionuclides during glass dissolution -- NATURAL GLASSES AND THE VERIFICATION OF THE LONG-TERM DURABILITY OF NUCLEAR WASTE GLASSES -- Selected References -- Actinide Vitrification: Status of Savannah River Site Activities -- Thermal Stability of Waste Form Glass -- MECHANICAL PROPERTIES OF THE WASTE FORM GLASS -- Abstract -- References -- Radiation Effects in Glass Waste Forms -- Review of Radiation Effects -- DOE Panel Findings -- References -- EXPERIENCE IN BELGIUM -- Operational experience of the Pamela Facility -- Quality Assurance Programme -- Recommendations for future Vitrification. -- Key-References -- VITRIFICATION EXPERIENCE IN FRANCE - DEVELOPMENT AND PERSPECTIVES -- EXPERIENCE IN THE UNITED STATES: WEST VALLEY, NEW YORK -- Introduction -- High-level Waste Pretreatment and Consolidation -- High-level Waste Vitrification Activities -- Conclusion -- Vitrification Experience of TVF in Japan -- ABSTRACT -- References -- Vitrification Experience in the UK -- Reference.

Experiences with Vitrification HLW and Development of New Approaches in Russia -- References -- Vitrification Experience in China -- COMPOSITION OF HLLW -- GLASS FRIT AND GLASS PRODUCT -- VITRIFICATION PROCESS -- Feed Preparation -- Vitrification -- Off Gas Treatment -- Canister Handling -- FEATURES OF FACILITY -- Melter Cell -- Melter -- TEST OF MELETER -- REFERENCES -- Vitrification Experience at the Defense Waste Processing Facility (DWPF) -- Natural Glasses as Analogs for Nuclear Waste Glasses -- Abstract -- References: -- ALTERATION OF NUCLEAR WASTE GLASSES CHARACTERIZED BY RADON EMANATION METHOD -- INTRODUCTION -- PRINCIPLE OF THE RADON EMANATION METHOD (REM) AND PREPARATION OFSAMPLES -- RESULTS AND DISCUSSION -- CONCLUSIONS -- REFERENCES -- ACKNOWLEDGMENTS -- DOE REGULATORY INITIATIVE FOR VITRIFIED MIXED WASTE -- Background -- DOE's Regulatory, Initiative -- Basis for Initiative -- Regulatory Control -- Waste Form Testing Strategy -- Summary and Conclusion -- Acknowledgments -- References -- Stabilization of Plutonium in Hybrid Glass Materials Using a Cyclone Melter -- Extended Abstract -- DOE REGULATORY INITIATIVE: IMMOBILIZED MIXED DEBRIS -- DOE'S PROPOSAL -- Integrity of the Final Waste Form -- Proposed Encapsulants -- Risk-Based Analysis of Low-Level Disposal Facilities -- SUMMARY -- Acknowledgments -- References -- Abstract -- Reexamination of Variables Affecting the Hydration of Obsidians Using Empirical Chronological Data and Laboratory Induced Hyd -- Statistical Analysis -- REFERENCES CITED: -- A PLASMA ARC - VITREOUS CERAMIC PROCESS FOR HAZARDOUS AND RADIOACTIVE WASTE STABILIZATION -- ABSTRACT -- REFERENCES -- DIRECT CONVERSION OF METALS, CERAMICS, AMORPHOUS SOLIDS, HALOGENS, AND ORGANICS TO BOROSILICATE GLASS USING THE GMODS PROCESS -- INTRODUCTION -- GMODS PROCESS DESCRIPTION -- STATUS OF LABORATORY WORK -- REFERENCES.

SURFACE LAYER FORMATION OF THE FRENCH SON68 NUCLEAR WASTE GLASS DURING VAPOR PHASE ALTERATION AT 200°C -- References -- POTENTIAL APPLICATION OF ELECTRON SPIN RESONANCE TO THE STUDY OF RADIATION EFFECTS IN HIGH-LEVEL NUCLEAR WASTE DISPOSAL GLASS -- LEACHING BEHAVIOR OF PU AND CM FROM WASTE GLASS UNDER REDUCING CONDITION -- ABSTRACT -- Glass and Glass-Ceramic Waste Forms Developed at the Idaho Chemical Processing Plant for Immobilizing HLW and Actinides -- REPRODUCTION OF NATURAL CORROSION BY ACCELERATED LABORATORY TESTINGMETHODS -- Vapor Hydration Tests on Tektite and Obsidian Glasses -- Nine-Year Results from Testing Basaltic and Simulated Waste Glasses -- REFERENCES -- COLLOID FORMATION DURING WASTE GLASS CORROSION -- REFERENCES -- Use Of DC Graphite Arc Melter Technology For Production Of Stable Vitrified Waste Forms -- Hanford Low Level Waste Melter Tests -- Experimental Determination of Uranium Oxide Solubility in Hydrous Silicate Melts of Granitic Composition -- Mixture Models Versus Free Energy of Hydration Models for Waste Glass Durability -- Abstract -- MICROSTRUCTURES AND LEACH RATES OF GLASS-CERAMIC WASTE FORMS FORIMMOBILIZING PLUTONIUM AND ASSOCIATED COMPONENTS -- Introduction -- Vitrification Under Pressure -- Vitrification In Ambient Atmosphere -- HOT ISOSTATIC PRESS (HIP) VITRIFICATION OF RADWASTE CONCRETES -- Reference: -- Waste Glass Leaching During Open Site Tests -- INTRODUCTION -- EXPERIMENTS AND RESULTS -- CONCLUSIONS -- REFERENCES -- In Situ Vitrification of Plutonium and Uranium Contaminated Buried Wastes: Microcompositional Analyses of Vitreous and... -- ISV Process -- Demonstrations on Plutonium and Uranium Contaminated Buried Wastes -- THE INTERACTION BETWEEN HLW GLASS AND CLAY: PRESENT STATUS AND FUTUREPROGRAMME. -- VERIFICATION STUDIES ON THE PAMELA HIGH-LEVEL WASTE GLASSES -- Synroc - an Alternative Waste Form.

CHEMISTRY OF IRRADIATED SOLIDS -- CORALUS: IN - SITU CORROSION TEST ON ACTIVE HLW GLASS -- 1. Objectives -- 2. Work Content -- Reference.