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Home arrow Environment arrow Nuclear Back-end and Transmutation Technology for Waste Disposal

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





Precise Measurements of Neutron Capture Cross Sections for LLFPs and MAsApplication of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy SupplyConsidering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom DebateOverviewNeutron SpectrumExperimentalResult of FRModification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality ControlOutline of the CoursesMYRRHA, A Research Tool in Support of the European Roadmap for P&TAnalysis Results for Doppler Feedback EnhancementMA Transmutation Core ConceptIssues for the FutureBurn-up SensitivityDesign of the Core and Primary SystemExperimental SetupDeveloped Uranium-Free TRU Metallic Core“Management of the Total Amount” of HLWThe Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and BudgetFour-Sensor ProbeI 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 DataModification of STACYDemand for Primary Energy and Electricity Is Increasing Year by YearPartitioning of 14C into Solid, Liquid, and Gas PhasesThorium-Loaded ADS BenchmarksFormation of an R&D Implementation and Evaluation TeamMYRRHA: A Flexible Fast-Spectrum Irradiation FacilityResult of FR+ADSAnalysis and Discussion of Neutron FluxDeciding the TopicReaction via Giant Dipole ResonanceOptions of Criticality Control PrinciplesTransfer of 14C from Soil to Rice PlantsTransmutation CalculationSample and Irradiation FacilityImpact on the RepositoryExpectation for Nuclear TransmutationDevelopment of a γ-Ray Spectrometer for NRCA/PGALicense Application and Schedule of the STACY ModificationSensitivity Calculation MethodSpecification Selected for Uranium-Free TRU Metallic CoreReduction of Prediction UncertaintyEffect of Irradiations on Surface WettabilityExperimental Setup and ProcedureConcerns on HLWSix Proposals by the Science Council of JapanRBWR-TBAccelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)Effect of Boiling Heat Transfer on Surface WettabilityParametric Analysis on the Effect of MeasuresNeutronics CalculationResearch and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage the Progress of Final DisposalResults and DiscussionScenario AnalysisDevelopment of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Application of a Self-Indication MethodBehavior of 14C in Rice Paddy FieldsDevelopment of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 x 9 FuelRequirements for Long-Term Knowledge ManagementSensitivity AnalysesMethodologyDesign of J-PARC Transmutation Experimental FacilityExperimental Study on Criticality Control for Fuel DebrisPresentation of MYRRHA and Its Role in the European P&T StrategyMA Transmutation RateConsideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated WaterCombustion MethodDesign of Core with MA-Hydride TargetThe Research and Development of Nuclear Technologies for Reactor Decommissioning, Safety Technology, Back-end, etc., Must Be Promoted Intensively Through International CooperationTarget Nuclides of Sensitivity AnalysesAnalyses ConditionsReflections on the CoursesRequirements for an Inventory List and Online Waste Management SystemUranium-Loaded ADS ExperimentsHeat Transfer Study for ADS Solid Target: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 AccidentPrevention of Severe ConsequenceRisk AssessmentTechnology for the Back-end of the Nuclear Fuel Cycle Must Be Enhanced. The Site for Final Disposal of Nuclear Wastes Must be Determined as SoonStudy on Neutron Spectrum of Pulsed Neutron ReactorMethod of Calculating Sensitivity CoefficientsResult of ADSAnalysis Results for Burnup Reactivity Swing ReductionCalculational Model and ConditionCalculation MethodResults and DiscussionEnhancement of Transmutation of Minor Actinides by Hydride TargetExperimental SettingsIV Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADSSafety Technology of Nuclear Energy Must Be Developed for the FuturePresent Condition of 1FNPS Fuel DebrisResults and DiscussionResult of LWR-PuTRBWR-TB2Results of the Questionnaire SurveyIssues of HLW Disposal in JapanOutline of TEF-PResult of LWR-OTSeparation Using Anion-SRPrevention of Criticality by Poison or Dry ProcessPerformance of the Uranium-Free TRU Metallic CoreFuture PlansHLW Disposal Program in JapanAssumption of Pu FeedThe MYRRHA AcceleratorDevelopment of Uranium-Free TRU Metallic Fuel Fast Reactor CoreSensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure MaterialsReagentsExperimentalSeparation Using Anion-SRNuclear Transmutation of 137Cs with Laser Compton ScatteringResearch MethodRBWR-ACDifficulty in Site SelectionVII Nuclear Fuel Cycle Policy and Technologies: National Policy, Current Status, Future Prospects and Public Acceptance of the Nuclear Fuel Cycle Including Geological DisposalComparison of Interfacial Area ConcentrationEnvironmental Transfer of Carbon-14 in Japanese Paddy FieldsDependence of Sensitivities on Numbers of Energy GroupsRBWR SystemRadial Profiles of Two-Phase Flow PropertiesResults and DiscussionSetting a Moratorium Period by “Temporal Safe Storage”Volume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation TechniqueWhy has Such a Situation Occurred?Electromagnetic ProbeDesign of MA-Hydride TargetComparison with Other NuclidesNotesMethod Development for Calculating Minor Actinide Transmutation in a Fast ReactorSurface Wettability Change by IrradiationCriticality Characteristics of Fuel DebrisResult of six-Batch CoreDiscussionThorium-Loaded ADS ExperimentsDevelopment of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daiichi Nuclear Power StationResult of One-Batch CoreV Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel CycleHigh-Energy Photons Obtained by Laser Compton ScatteringContact Angle MeasurementScenario AnalysisBackground and ObjectivesPrevention of Criticality by MonitoringCombustion MethodPresent Situation of Data for LLFPs and MAsDevelopment of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Application of a Self-Indication MethodResults and DiscussionCurrent Status of HLWTheory of Power Spectral Density and Feynman-Alpha Method in AcceleratorDriven System and Their Higher-Order Mode EffectsThe Molten Salt ReactorOverview of European Experience with Thorium FuelsThorium European Research Programme HistoryParametric Analysis MethodologyExperiment at KUCA and Measured ResultsThe Concept of NRDCore Calculation MethodDesign of Spallation Target for TEF-TPrinciple of Ferrocyanide Coprecipitation for Cs RemovalTh-MOX Fuels Irradiated in LWR ConditionsContribution of the European Commission to a European Strategy for HLW Management Through Partitioning & TransmutationOptions of Principles of Fuel Debris Criticality Control in Fukushima Daiichi ReactorsTheory of Power Spectral Density in ADSTransmutation Scenarios after Closing Nuclear Power PlantsConcept of Geological Disposal and RiskExperiments for NRD DevelopmentsResults of Sensitivity AnalysesRecent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear Materials in Particle-Like DebrisIssues and Measures Against the Uranium-Free TRU Metallic Fast Reactor CoreIX Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear WastesCritical Experiments on Criticality Safety for Fuel DebrisResults and DiscussionTheory of Feynman-α Method in ADSNuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical ApproachGlobal Warming Is Becoming a More Serious ProblemNeutron Flux DistributionVIII Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the Environment Monitored After the Accidents at TEPCO's Nuclear Power StationsReference ADS (MA-ADS)Experimental Study of Flow Structure and Turbulent Characteristics in Lead– Bismuth Two-Phase FlowInvolvement of Microorganisms in the 14C BehaviorSensitivity Analysis Using the Initial Composition Based on Measured DataII Development of ADS Technologies: Current Status of Accelerator-Driven System DevelopmentUranium-Loaded ADS ExperimentsTransmutation Half-LifeNeutron Resonance DensitometryOutline of TEF-TExperimentHuman Beings Cannot Avoid Depending on Nuclear Energy as Well as Other Energy Resources, Including Renewable Energy, Which Do Not Emit CO2A Rough Draft of an NRD FacilityAnalytical ProcedureIII Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material EngineeringRelated Technologies for ADS and Other Advanced Reactor SystemsDiscussionSetup of the Calculation for 137CsBubble-Induced TurbulenceAwareness of the Limits of Scientific and Technical AbilitiesManufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]ADS Design for Pu TransmutationMeasurement Activities at J-PARC/MLF/ANNRIOutline of the Transmutation Experimental FacilityMeasurement Activities by the Activation MethodMeasurement TechniquesThe Situation NowSensitivity to Infinite-Dilution Cross SectionDevelopment Strategy of Waste Treatment, Storage, Transport, and Disposal TechnologiesNuclear Technology Must be DevelopedResults and DiscussionNumerical Results and Discussion
 
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