Sodium Fast Reactors with Closed Fuel Cycle

BASIS AND CONCEPTSNuclear Fission and BreedingIntroductionAbout the NeutronNucleus StabilityEnergy from FissionFission Neutrons and Energy SpectrumChain ReactionFissile and Fertile MaterialsAbout BreedingWorking of Nuclear ReactorsReactor Control and Safety: Reactor PhysicsReferencesFast Spectrum Reactor vis-a-vis Pressurized Water ReactorsIntroductionNeutronic CharacteristicsSafety CharacteristicsGeometric Features of CoreReferencesDescription of a Fast Spectrum ReactorIntroductionCore and Reactor AssemblyMain Heat Transport SystemComponent HandlingSteam-Water SystemElectrical Power SystemsInstrumentation and ControlUnique Worthiness of SFRIntroductionUranium Utilization in the Open Fuel Cycle ModeUranium Utilization in the Closed Fuel Cycle ModeFuel Utilization in the Fast Breeder Reactor: A Case StudyHigh-Level Radioactive Waste Management and Environmental IssuesMinor Actinide Burning Design ConceptsTypical Minor Actinide Burning Scenario in Fast Spectrum Reactors (FSRs)ReferencesDesign Objectives for the Efficient Use of Natural Uranium and PlutoniumIntroductionGrowthPerformance and Fuel Consumption AspectsReferencesProspect of Various Types of FSRsIntroductionSodium-Cooled Fast ReactorsLead-Cooled Fast ReactorsMolten Salt ReactorsGas-Cooled Fast ReactorsComparison of Advanced Fast Reactors with SFRsFast Reactors That Evolved Post-FukushimaReferencesDESIGN OF SODIUM FAST REACTORSChoice of Materials and Their PerformanceIntroductionFuelCore Structural MaterialsReactor StructuresCoolantReferencesSystem and ComponentsIntroductionReactor CoreNuclear Steam Supply SystemReactor MechanismsInstrumentation and Control SystemEnergy Conversion SystemsReferencesDesign BasisIntroductionFailure ModesCodes and StandardsDesign Criteria for the Aspects Not Covered in RCC-MR/ASMEThermal Hydraulic Design CriteriaReferencesDesign ValidationsIntroductionStructural Analysis Codes and Structural Design MethodologyThermal Hydraulic CodesLarge-Scale Experimental ValidationsExperimental Facilities for Qualification of SFR Components in IndiaAppendix A: 23-Parameter Chaboche Viscoplastic ModelAppendix B: 20-Parameter Viscoplastic Model for 9Cr-1Mo SteelReferencesDesign Analysis and MethodsIntroductionReactor PhysicsThermal HydraulicsStructural Mechanics Analysis of Special Problems Relevant to SFRReferencesSAFETYSafety Principles and PhilosophyIntroductionInherent and Engineered Safety FeaturesOperation SimplicityRadioactivity ReleaseReferencesSafety Criteria and BasisIntroductionGeneric Features of Fast Reactors to Be Addressed in the Safety CriteriaSafety Issues Related to Sodium to Be Addressed in the Safety CriteriaIAEA and Other International Safety StandardsSafety Criteria for SFR: A Few HighlightsEvolving TrendsReferencesEvent AnalysisIntroductionCategorization of Events: Basis, Definition, and ExplanationMethodology of AnalysisApplication of Plant Dynamics StudySummaryReferencesSevere Accident AnalysisIntroductionInitiating EventsSevere Accident ScenariosMechanical Energy Release and ConsequencesPostaccident Heat RemovalRadiological ConsequencesReferencesSodium SafetyIntroductionSodium FireSodium-Water InteractionSodium-Concrete InteractionSodium Fire MitigationReferencesComputer Codes and ValidationIntroductionComputer Codes for Severe Accident AnalysisComputer Codes for the Mechanical ConsequencesRadioactive ReleaseSodium Fire CodesReferencesTest Facilities and ProgramsIntroductionOverview of Test Facilities Related to Core SafetyOverview of Test Facilities Related to Molten Fuel-Coolant InteractionsTest Facilities Related to Postaccident Heat RemovalTest Facilities Related to Sodium SafetyReferencesSafety Experiments in ReactorsIntroductionHighlights of Safety ExperimentsConclusionReferencesSevere Accident ManagementIntroductionAnalysis for the Consequences of Design Extension Conditions: PFBR Case StudyImproved Safety Features for Future SFRsSummaryReferencesSafety Analysis of PFBR: A Case StudyIntroductionSafety Features Incorporated in PFBRSevere Accident AnalysisAssessment of Primary Containment Potential: Highlights of AnalysisSodium Leak through Top Shield and Containment Design PressureTemperature and Pressure Rise in RCBExperimental SimulationsPostaccident Heat RemovalSite Boundary DoseSummaryReferencesCONSTRUCTION AND COMMISSIONINGSpecific Aspects of Civil Structures and ConstructionIntroductionSpecific Aspects of Reactor BuildingsChallenges in Civil ConstructionReferencesManufacturing and Erection of Mechanical ComponentsSpecific Features of SFR Components w.r.t. Manufacturing and ErectionManufacturing and Erection Tolerances: Basis and ChallengesManufacturing Codes and PracticesSummaryReferencesIllustrations from International SFRsMonjuSuper Phenix (SPX1)500 MWe Prototype Fast Breeder ReactorSummaryReferencesCommissioning Issues: Various Phases and ExperiencesFast Flux Test FacilityPhneixBN-600 Reactor Commissioning ExperienceReferencesINTERNATIONAL SFR EXPERIENCESSFR Program in CountriesIntroductionChinaFranceGermanyIndiaJapanKoreaRussiaUnited StatesReferencesFeedback from Operating ExperiencesIntroductionDesign ConceptsMaterial BehaviorSafety ExperienceOperational ExperienceReferencesInnovative Reactor Concepts for Future SFRsMotivation, Strategies, and ApproachesINPRO: Closed Fuel Cycle with Fast Reactor (CNFC-FR)Concepts Specific to NationsReferencesFUEL CYCLE FOR SFRSFuel Cycle for SFRsIntroductionOpen and Closed Fuel CycleClosed Fuel Cycle for Fast ReactorsFuel TypesPerformance Requirements of Fast Reactor FuelsFuel Fabrication ProcessesFuel ReprocessingAqueous ReprocessingSpecial Features of Fast Reactor Fuel ReprocessingInternational Experience on Fast Reactor Fuel ReprocessingPyrochemical ReprocessingReprocessing of Carbide and Nitride FuelsPartitioning of Minor ActinidesWaste Management for Fast Reactor Fuel CycleFast Reactors and Minor Actinides BurningConclusionReferencesDECOMMISSIONING ASPECTSDecommissioning AspectsIntroductionMajor Difference between Decommissioning Aspects of SFR and PWRMajor Activities and Challenges Involved in Decommissioning of SFRTechnological StrategiesExperience and Feedback from Reactor DecommissioningSummaryReferencesBibliographyDOMAINS OF HIGH RELEVANCE TO SFR: TYPICAL EXAMPLESMaterial Science and MetallurgyIntroductionCore Structural MaterialsRadiation-Resistant SteelsIon Beam SimulationComputer SimulationCompatibility of Clad Material with Coolant and FuelReactor Structural MaterialsSteam Generator MaterialsHardfacingSummaryReferencesChemical Sensors for Sodium Coolant CircuitsIntroductionSensors for Monitoring Dissolved Hydrogen in Liquid SodiumSensors for Monitoring Carbon Activity in Liquid SodiumSensors for Monitoring Oxygen in Liquid Sodium SystemsReferencesRobotics, Automation, and SensorsIntroductionIn-Service Inspection of Components of Fast Breeder ReactorRemote Handing Tools and Robotic Devices for Nuclear Fuel Cycle FacilitiesSensors for Robotics and AutomationSummaryReferencesOperator Training Simulators for Fast Breeder ReactorsIntroductionTypes of SimulatorsOperator Training SimulatorBasic Simulator ModelDesign and Development of Training SimulatorIntegration and Performance TestingVerification and Validation of Training SimulatorImplementationConfiguration Management of Training SimulatorReference StandardsECONOMICS OF SFRS WITH A CLOSED FUEL CYCLEEconomics of SFRs with a Closed Fuel CycleIntroductionOverall Perception on the Economy of SFRsEconomic Assessment of International SFRsFuture Directions: Technological ChallengesApproach to Economics of SFR in India: A Case StudyReferences