Sodium Fast Reactors with Closed Fuel Cycle

Sodium Fast Reactors with Closed Fuel Cycle delivers a detailed discussion of an important technology that is being harnessed for commercial energy production in many parts of the world. Presenting the state of the art of sodium-cooled fast reactors with closed fuel cycles, this book: Offers in-depth coverage of reactor physics, materials, design, safety analysis, validations, engineering, construction, and commissioning aspects Features a special chapter on allied sciences to highlight advanced reactor core materials, specialized manufacturing technologies, chemical sensors, in-service inspection, and simulators Addresses design essentials with a focus on reactor assembly including core and coolant circuits, fuel handling, instrumentation and control, energy conversion, and containment systems Provides design codes and standards with sufficient background information to ensure a solid understanding of the underlying mechanics Supplies guidelines for concept selection, design, analysis, and validation Sodium Fast Reactors with Closed Fuel Cycle is a valuable reference for industry professionals involved in the construction of fast-reactor power plants, as well as graduate-level engineering students of the design and development of sodium-cooled fast-reactor systems and components.

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-à-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 FacilityPhnéixBN-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

Baldev Raj, BE, Ph.D, served the Department of Atomic Energy, India over a 42-year period until 2011. As distinguished scientist and director, Indira Gandhi Centre of Atomic Research, Kalpakkam, India (IGCAR), he has advanced several challenging technologies, especially those related to the fast breeder test reactor and the prototype fast breeder reactor. Dr. Raj pioneered the application of nondestructive examination (NDE) for basic research using acoustic and electromagnetic techniques in a variety of materials and components. He is also responsible for realizing societal applications of NDE in areas related to cultural heritage and medical diagnosis. He is the author of more than 970 refereed publications, 70 books, and special journal volumes, and more than 20 contributions to encyclopedias and handbooks, as well as the owner of 29 patents. He is immediate past president, International Institute of Welding and President, Indian National Academy of Engineering. He assumed responsibilities as the director of the National Institute of Advanced Studies, Bangalore, India in September 2014. He is a fellow of all science and engineering academies in India; member of the German Academy of Sciences; honorary member of the International Medical Sciences Academy; member of the International Nuclear Energy Academy; vice president, nondestructive testing, Academia International; and president-elect of the International Council of Academies of Engineering and Technological Sciences. P. Chellapandi, BE (Hons.), M.Tech., Ph.D, is currently a distinguished scientist and director of the Reactor Design Group at the IGCAR. He specializes in reactor design, thermal hydraulics, structural mechanics, safety analysis, and experimental simulations. He is one of the key persons involved in the design and development activities of the 500 MWe prototype fast breeder reactor (PFBR) since its inception. He has contributed significantly for the PFBR over a wide spectrum of design, analysis, qualification, and research activities, also involving academic and R&D institutions in the country. His current responsibilities include design of advanced oxide and metallic fast breeder reactors planned by the department. He is a senior professor at Homi Bhabha National Institute and has published about 130 journal papers. He is a fellow at the Indian National Academy of Engineering. He is the recipient of the Homi Bhabha Science and Technology Award; the Indian Nuclear Society Award; the Vasvik Award; the National Design Award in Mechanical Engineering from Institute of Electrical and Electronics Engineers; the Agni Award for Excellence in Self-Reliance from Defence Research and Development Organization; the Department of Atomic Energy (DAE) Group Achievement Award for the design, manufacture, and erection of PFBR reactor assembly components; and the Distinguished Alumnus Award from the Indian Institute of Technology, Chennai. P.R. Vasudeva Rao, B.Sc., Ph.D, is the director of the IGCAR and the General Services Organization at Kalpakkam, India. After graduating from Vivekananda College, Chennai, India, he joined the DAE in the 16th batch of Bhabha Atomic Research Centre training school. He was instrumental in the setting up of the Radiochemistry Laboratory at the IGCAR. He is an expert in the area of fast reactor fuel cycle, especially the back-end fuel cycle. He is a recipient of the Indian Nuclear Society Award (2007) for his contributions to the area of nuclear fuel cycle technologies. He was selected for the Material Research Society of India (MRSI) medal lecture in 1998 and MRSI-ICSC Superconductivity and Materials Science Senior Award in 2011. He was also selected for the award of the Silver Medal by the Chemical Research Society of India in 2011. He is a senior professor at the Homi Bhabha National Institute. He has nearly 250 publications in peer-reviewed international journals. His areas of interest include the development of technologies for fast reactors and associated fuel cycles, actinide separations, and education in the field of chemical sciences.