NUCLEAR POWER: TECHNICAL AND INSTITUTIONAL OPTIONS FOR THE FUTURE

By ANDREW LEWIS

NONTRADITIONAL CERAMIC FUELS CARBIDE FUELS NITRIDE FUELS OTHER NONTRADITIONAL CERAMIC FUEL FORMS COATED PARTICLE FUELS CO FORMATION AND THE EFFECT ON PARTICLE INTEGRITY FISSION PRODUCT CHEMISTRY AND TRANSPORT IN TRISTRUCTURAL ISOTROPIC FUEL PARTICLES OXYGEN POTENTIAL AND FISSION PRODUCTS SUMMARY AND OUTLOOK REFERENCES FURTHER READING MOLTEN SALT REACTOR FUELS INTRODUCTION KEY ADVANTAGES OF THE MOLTEN SALT REACTOR CHALLENGES FOR MOLTEN SALT REACTOR DEPLOYMENT HISTORY OF MOLTEN SALT REACTOR RESEARCH MOLTEN SALT REACTOR RENAISSANCE MOLTEN SALT REACTOR FUEL CONCEPTS FUEL SALT PROPERTIES MELTING POINT VAPOR PRESSURE—BOILING POINT HEAT CAPACITY SOLUBILITY OF ACTINOIDS FISSION PRODUCT RETENTION STABILITY TO RADIATION MEASUREMENTS AND EXPERIMENTAL PROCEDURES HANDLING SAMPLE SYNTHESIS AND PURIFICATION HIGH-TEMPERATURE MEASUREMENTS—ENCAPSULATION REDOX POTENTIAL OF THE FUEL CORROSION INHIBITION FISSION PRODUCT SPECIATION MONITORING OF REDOX POTENTIAL DURING REACTOR OPERATION EFFECT OF OXYGEN IMPURITIES EFFECT OF SOLUBLE FISSION PRODUCT IMPURITIES CONCLUSION RESEARCH REACTOR FUELS FUEL GEOMETRY PLATE-TYPE FUELS TUBULAR FUELS ROD- AND PIN-TYPE FUELS FUEL MATERIALS EVOLUTION OF RESEARCH REACTOR FUEL DURING OPERATION FABRICATION PROCESSES FUEL BEHAVIOR UNDER IRRADIATION URANIUM ALUMINIDES URANIUM SILICIDES URANIUM OXIDES URANIUMMOLYBDENUM ALLOYS URANIUMZIRCONIUM HYDRIDE FUEL CORROSION OF ALUMINUM RESEARCH REACTOR FUEL CLADDING PART C STAGES OF THE FUEL CYCLE AND OTHER APPLICATIONS MINING AND MILLING MINING URANIUM RESOURCES URANIUM BEARING MINERALS MINING METHODS MILLING ION EXCHANGE SOLVENT EXTRACTION PRECIPITATION TAILINGS SUMMARY URANIUM CONVERSION AND ENRICHMENT NATURAL URANIUM CONVERSION PROCESSES WHAT IS URANIUM CONVERSION? THE SPECIAL ROLE OF UF6 IN THE NUCLEAR FUEL CYCLE PRODUCTION OF CERAMIC-GRADE UO2 FOR PRESSURIZED HEAVY-WATER REACTORS PRODUCTION OF URANIUM METAL FOR MAGNOX REACTORS URANIUM ENRICHMENT URANIUM ENRICHMENT PROCESSES WET CONVERSION PROCESSES DRY CONVERSION PROCESSES CONCLUSION AND FUTURE TRENDS ADVANCES IN FUEL FABRICATION CERAMIC FUEL FABRICATION OXIDE FUEL FABRICATION NITRIDE FUEL FABRICATION OTHER CERAMIC FUEL FABRICATION METALLIC FUEL FABRICATION INTRODUCTION TO METALLIC FUELS FABRICATION METHODS FOR METALLIC FUELS ADVANCED REACTOR FUEL FABRICATION HIGH-DENSITY LIGHT-WATER REACTOR FUELS COATED PARTICLE FUEL FABRICATION MOLTEN-SALT REACTOR FUEL FABRICATION ACKNOWLEDGMENTS IN-REACTOR BEHAVIOR GENERAL DESCRIPTION OF FUEL BEHAVIOR THERMAL AND FAST REACTOR FUELS RADIATION DAMAGE—IRRADIATION EFFECTS MICROSTRUCTURAL EVOLUTION FUEL SWELLING OXIDE FUEL CHEMISTRY UO2 AND (U,PU)O2 OXIDES IRRADIATED OXIDE FUEL OTHER FUELS CHEMISTRY IRRADIATED FUEL CHEMISTRY FUELCLADDING CHEMICAL INTERACTION CONCLUSION—OUTLOOKS REPROCESSING AND RECYCLING CHARACTERISTICS OF USED NUCLEAR FUEL REUSE OF URANIUM FROM USED LIGHT-WATER REACTOR FUEL ZIRCONIUM RECYCLE AND DISPOSITION OPTIONS HARDWARE COMPONENT RECYCLE ADDITIONAL COMPONENT RECYCLE HEADEND PROCESSING OF ZIRCALOY-CLAD FUELS FOR HYDROMETALLURGICAL SEPARATIONS DISASSEMBLY AND DECLADDING VOLOXIDATION NITRIC ACID DISSOLUTION CLARIFICATION AND ACCOUNTING DISPOSITION OF CLADDING HEADEND PROCESSING FOR ALTERNATIVE OR ADVANCED FUELS TRISO FUELS THE PROCESS OF DIRECT USE OF PRESSURIZED WATER REACTOR FUEL IN CANDU THORIUM-ENHANCED FUELS OFF-GAS TREATMENT AND EMISSION CONTROLS IODINE TRITIUM KRYPTON NOBLE METALS AND OTHER SEMIVOLATILES SEPARATIONS HYDROMETALLURGICAL SEPARATIONS—SOLVENT EXTRACTION HYBRID AQUEOUS PROCESSING PYROCHEMICAL PROCESSES FLUORIDE VOLATILITY CHLORIDE VOLATILITY SPENT NUCLEAR FUEL AND DISPOSAL INTRODUCTION—GENERALITIES ON SPENT NUCLEAR FUEL SPENT NUCLEAR FUEL MANAGEMENT STRATEGIES, CLOSED VERSUS OPEN NUCLEAR CYCLES SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTE STORAGE—INTERNATIONAL PRACTICES WET STORAGE DRY STORAGE SPENT NUCLEAR FUEL AND HIGH-LEVEL WASTE GEOLOGICAL DISPOSAL— INTERNATIONAL PRACTICES KEY PROCESSES FROM OPERATION TO DISPOSAL THROUGH STORAGE THAT IMPACT THE LONG-TERM STABILITY OF SPENT NUCLEAR FUEL DISSOLUTION AND ALTERATION OF SPENT NUCLEAR FUEL UNDER DEEP GEOLOGICAL REPOSITORY CONDITIONS OUTLOOK APPENDIX ADVANCES IN FUEL CHEMISTRY DURING A SEVERE ACCIDENT CHEMISTRY ON FUEL/CORE DEGRADATION CHEMISTRY IN EARLY PHASE FUEL DEGRADATION CHEMISTRY IN TRANSITION FROM EARLY PHASE TO LATE PHASE CHEMISTRY IN LATE PHASE DEGRADATION CHEMISTRY ON FUEL DEGRADATION EX-VESSEL CONDITIONS FISSION PRODUCT CHEMISTRY AT SEVERE ACCIDENT OF LIGHT WATER REACTORS CHEMISTRY OF FISSION PRODUCT RELEASE FROM IRRADIATED FUEL DURING SEVERE ACCIDENT FISSION PRODUCT CHEMISTRY IN REACTOR COOLANT SYSTEM, GAS PHASE, AND INTERACTIONS WITH STRUCTURE SURFACE FISSION PRODUCT CHEMISTRY IN CONTAINMENT, GAS PHASE, AND INTERACTIONS WITH CONTAINMENT SURFACES CHEMISTRY IN CONTAINMENT POOLS AND IN LIQUID SCRUBBER CONTAINMENT VENTING SYSTEMS PART A FUNDAMENTALS