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A short course of lectures
«Nuclear Back-end and Transmutation Technology for Waste Disposal»





Measurement TechniquesRBWR SystemThe Molten Salt ReactorCalculation MethodAnalysis Results for Burnup Reactivity Swing ReductionOptions of Criticality Control PrinciplesResults and DiscussionResearch and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage the Progress of Final DisposalSensitivity Calculation MethodDesign of Spallation Target for TEF-TPartitioning of 14C into Solid, Liquid, and Gas PhasesTheory of Power Spectral Density and Feynman-Alpha Method in AcceleratorDriven System and Their Higher-Order Mode EffectsPrevention of Criticality by Poison or Dry ProcessOutline of TEF-PV Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel CycleDemand for Primary Energy and Electricity Is Increasing Year by YearRecent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear Materials in Particle-Like DebrisReaction via Giant Dipole ResonanceDesign of J-PARC Transmutation Experimental FacilityFour-Sensor ProbeResults of the Questionnaire SurveyExperimental Study of Flow Structure and Turbulent Characteristics in Lead– Bismuth Two-Phase FlowScenario AnalysisFuture PlansIV Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADSWhy has Such a Situation Occurred?Experiment at KUCA and Measured ResultsSpecification Selected for Uranium-Free TRU Metallic CoreHeat Transfer Study for ADS Solid Target:Comparison of Interfacial Area ConcentrationBehavior of 14C in Rice Paddy FieldsFormation of an R&D Implementation and Evaluation Team“Management of the Total Amount” of HLWNuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical ApproachHigh-Energy Photons Obtained by Laser Compton ScatteringAnalyses ConditionsModification of STACYResults and DiscussionAssumption of Pu FeedConcept of Geological Disposal and RiskBubble-Induced TurbulenceCriticality Characteristics of Fuel DebrisExperimental SettingsRBWR-ACPresent Situation of Data for LLFPs and MAsDeveloped Uranium-Free TRU Metallic CoreSix Proposals by the Science Council of JapanCombustion MethodSensitivity Analysis Using the Initial Composition Based on Measured DataRisk AssessmentUranium-Loaded ADS ExperimentsDifficulty in Site SelectionAnalytical ProcedureIssues for the FutureMethod Development for Calculating Minor Actinide Transmutation in a Fast ReactorPrevention of Criticality by MonitoringMeasurement Activities at J-PARC/MLF/ANNRIThorium European Research Programme HistoryConsideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated WaterTechnology for the Back-end of the Nuclear Fuel Cycle Must Be Enhanced. The Site for Final Disposal of Nuclear Wastes Must be Determined as SoonAnalysis and Discussion of Neutron FluxExperimental SetupParametric Analysis on the Effect of MeasuresResults and DiscussionReflections on the CoursesOverview of European Experience with Thorium FuelsExperimental Setup and ProcedurePerformance of the Uranium-Free TRU Metallic CoreResult of FR+ADSImpact on the RepositoryResults and DiscussionPrecise Measurements of Neutron Capture Cross Sections for LLFPs and MAsOutline of TEF-TVIII Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the Environment Monitored After the Accidents at TEPCO's Nuclear Power StationsRBWR-TBThe Situation NowSample and Irradiation FacilityInvolvement of Microorganisms in the 14C BehaviorMYRRHA, A Research Tool in Support of the European Roadmap for P&TOverviewGlobal Warming Is Becoming a More Serious ProblemSensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure MaterialsPresentation of MYRRHA and Its Role in the European P&T StrategyExperimentTransmutation Scenarios after Closing Nuclear Power PlantsBackground and ObjectivesThe Research and Development of Nuclear Technologies for Reactor Decommissioning, Safety Technology, Back-end, etc., Must Be Promoted Intensively Through International CooperationCurrent Status of HLWVII Nuclear Fuel Cycle Policy and Technologies: National Policy, Current Status, Future Prospects and Public Acceptance of the Nuclear Fuel Cycle Including Geological DisposalADS Design for Pu TransmutationI Basic Research for Nuclear Transmutation and Disposal: Physical and Chemical Studies Relevant to Nuclear Transmutation and Disposal Such as Measurement or Evaluation of Nuclear Cross-Section DataPresent Condition of 1FNPS Fuel DebrisNeutron Flux DistributionUranium-Loaded ADS ExperimentsSeparation Using Anion-SREnvironmental Transfer of Carbon-14 in Japanese Paddy FieldsResults of Sensitivity AnalysesHLW Disposal Program in JapanDevelopment of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daiichi Nuclear Power StationAnalysis Results for Doppler Feedback EnhancementDependence of Sensitivities on Numbers of Energy GroupsTh-MOX Fuels Irradiated in LWR ConditionsIssues and Measures Against the Uranium-Free TRU Metallic Fast Reactor CoreResult of six-Batch CoreResults and DiscussionMA Transmutation Core ConceptRBWR-TB2Result of ADSA Rough Draft of an NRD FacilityOutline of the CoursesNotesResult of FRTransmutation Half-LifeMYRRHA: A Flexible Fast-Spectrum Irradiation FacilityDevelopment Strategy of Waste Treatment, Storage, Transport, and Disposal TechnologiesDesign of MA-Hydride TargetOptions of Principles of Fuel Debris Criticality Control in Fukushima Daiichi ReactorsThe Concept of NRDDesign of the Core and Primary SystemRequirements for Long-Term Knowledge ManagementSensitivity to Infinite-Dilution Cross SectionResearch MethodII Development of ADS Technologies: Current Status of Accelerator-Driven System DevelopmentNeutron SpectrumResult of One-Batch CoreMeasurement Activities by the Activation MethodAwareness of the Limits of Scientific and Technical AbilitiesMethod of Calculating Sensitivity CoefficientsConcerns on HLWThorium-Loaded ADS BenchmarksResults and DiscussionTheory of Feynman-α Method in ADSSurface Wettability Change by IrradiationVolume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation TechniqueManufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]Burn-up SensitivityModification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality ControlThe Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and BudgetLicense Application and Schedule of the STACY ModificationResult of LWR-OTSetting a Moratorium Period by “Temporal Safe Storage”III Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material EngineeringRelated Technologies for ADS and Other Advanced Reactor SystemsMethodologyStudy on Neutron Spectrum of Pulsed Neutron ReactorEnhancement of Transmutation of Minor Actinides by Hydride TargetResults and DiscussionApplication of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy SupplyNeutron Resonance DensitometryAccelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)VI Reactor Physics Studies for Post Fukushima Accident Nuclear Energy: Studies from the Reactor Physics Aspect for Back-End Issues Such as Treatment of Debris from the Fukushima AccidentContact Angle MeasurementOutline of the Transmutation Experimental FacilityDiscussionNuclear Transmutation of 137Cs with Laser Compton ScatteringCombustion MethodThorium-Loaded ADS ExperimentsParametric Analysis MethodologyReference ADS (MA-ADS)Transmutation CalculationNumerical Results and DiscussionNuclear Technology Must be DevelopedRequirements for an Inventory List and Online Waste Management SystemSafety Technology of Nuclear Energy Must Be Developed for the FutureReduction of Prediction UncertaintyDevelopment of a γ-Ray Spectrometer for NRCA/PGAExperimental Study on Criticality Control for Fuel DebrisNeutronics CalculationIssues of HLW Disposal in JapanHuman Beings Cannot Avoid Depending on Nuclear Energy as Well as Other Energy Resources, Including Renewable Energy, Which Do Not Emit CO2DiscussionExperiments for NRD DevelopmentsEffect of Irradiations on Surface WettabilityResult of LWR-PuTExperimentalConsidering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom DebateMA Transmutation RateCalculational Model and ConditionPrinciple of Ferrocyanide Coprecipitation for Cs RemovalExperimentalSetup of the Calculation for 137CsIX Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear WastesEffect of Boiling Heat Transfer on Surface WettabilitySensitivity AnalysesElectromagnetic ProbeDesign of Core with MA-Hydride TargetExpectation for Nuclear TransmutationTarget Nuclides of Sensitivity AnalysesCore Calculation MethodCritical Experiments on Criticality Safety for Fuel DebrisDevelopment of Uranium-Free TRU Metallic Fuel Fast Reactor CoreThe MYRRHA AcceleratorRadial Profiles of Two-Phase Flow PropertiesDevelopment of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Application of a Self-Indication MethodDevelopment of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Application of a Self-Indication MethodReagentsDevelopment of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 x 9 FuelSeparation Using Anion-SRTransfer of 14C from Soil to Rice PlantsDeciding the TopicScenario AnalysisComparison with Other NuclidesPrevention of Severe ConsequenceTheory of Power Spectral Density in ADSContribution of the European Commission to a European Strategy for HLW Management Through Partitioning & Transmutation
 
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