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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»





Target Nuclides of Sensitivity AnalysesIV Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADSAnalysis Results for Doppler Feedback EnhancementAnalysis Results for Burnup Reactivity Swing ReductionResult of ADSHeat Transfer Study for ADS Solid Target:Development Strategy of Waste Treatment, Storage, Transport, and Disposal TechnologiesNeutron SpectrumBehavior of 14C in Rice Paddy FieldsOutline of TEF-PResults and DiscussionPrevention of Criticality by MonitoringNuclear Technology Must be DevelopedTheory of Feynman-α Method in ADSExperimental Setup and ProcedureNeutron Resonance DensitometryIssues for the FutureV Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel CyclePresent Situation of Data for LLFPs and MAsAwareness of the Limits of Scientific and Technical AbilitiesHigh-Energy Photons Obtained by Laser Compton ScatteringConcerns on HLWConcept of Geological Disposal and RiskExperimental Study on Criticality Control for Fuel DebrisResults of the Questionnaire SurveyDemand for Primary Energy and Electricity Is Increasing Year by YearMethodologyRadial Profiles of Two-Phase Flow PropertiesThorium European Research Programme HistoryStudy on Neutron Spectrum of Pulsed Neutron ReactorEnvironmental Transfer of Carbon-14 in Japanese Paddy FieldsElectromagnetic ProbeResults and DiscussionResult of LWR-OTExperimental Study of Flow Structure and Turbulent Characteristics in Lead– Bismuth Two-Phase FlowDeciding the TopicEffect of Irradiations on Surface WettabilityDesign of J-PARC Transmutation Experimental FacilityDevelopment of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daiichi Nuclear Power StationPerformance of the Uranium-Free TRU Metallic CoreReflections on the CoursesThorium-Loaded ADS BenchmarksRecent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear Materials in Particle-Like DebrisAnalyses ConditionsMethod of Calculating Sensitivity CoefficientsDesign of the Core and Primary SystemResult of FRResult of six-Batch CoreGlobal Warming Is Becoming a More Serious ProblemCombustion MethodInvolvement of Microorganisms in the 14C BehaviorMYRRHA: A Flexible Fast-Spectrum Irradiation FacilityResult of FR+ADSParametric Analysis MethodologyDevelopment of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Application of a Self-Indication MethodSensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure MaterialsExperimentalAnalytical ProcedureSample and Irradiation FacilityDesign of MA-Hydride TargetSix Proposals by the Science Council of JapanComparison with Other NuclidesDevelopment of Uranium-Free TRU Metallic Fuel Fast Reactor CoreExperiments for NRD DevelopmentsNuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical ApproachSeparation Using Anion-SRThe Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and BudgetHuman Beings Cannot Avoid Depending on Nuclear Energy as Well as Other Energy Resources, Including Renewable Energy, Which Do Not Emit CO2Method Development for Calculating Minor Actinide Transmutation in a Fast ReactorResults and DiscussionSensitivity to Infinite-Dilution Cross SectionSafety Technology of Nuclear Energy Must Be Developed for the FutureIssues of HLW Disposal in JapanOutline of TEF-TResults and DiscussionI 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 DataExperiment at KUCA and Measured ResultsThorium-Loaded ADS ExperimentsNeutronics CalculationExperimentBurn-up SensitivityNotesPrecise Measurements of Neutron Capture Cross Sections for LLFPs and MAsOutline of the CoursesTransmutation Scenarios after Closing Nuclear Power PlantsResearch and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage the Progress of Final DisposalModification of STACYCurrent Status of HLWSensitivity Analysis Using the Initial Composition Based on Measured DataPrinciple of Ferrocyanide Coprecipitation for Cs RemovalModification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality ControlWhy has Such a Situation Occurred?The Concept of NRDDifficulty in Site SelectionMYRRHA, A Research Tool in Support of the European Roadmap for P&TApplication of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy SupplyReaction via Giant Dipole ResonanceResearch MethodDiscussionPrevention of Criticality by Poison or Dry ProcessCalculational Model and ConditionCore Calculation MethodDesign of Core with MA-Hydride TargetManufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]ExperimentalCombustion MethodTheory of Power Spectral Density and Feynman-Alpha Method in AcceleratorDriven System and Their Higher-Order Mode EffectsRisk AssessmentTheory of Power Spectral Density in ADSVolume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation TechniqueDiscussionPresentation of MYRRHA and Its Role in the European P&T StrategyFour-Sensor ProbeResults and DiscussionParametric Analysis on the Effect of MeasuresImpact on the RepositoryTransfer of 14C from Soil to Rice PlantsContribution of the European Commission to a European Strategy for HLW Management Through Partitioning & TransmutationThe Molten Salt ReactorHLW Disposal Program in JapanCritical Experiments on Criticality Safety for Fuel DebrisNeutron Flux DistributionSensitivity Calculation MethodExperimental SettingsReagentsOutline of the Transmutation Experimental FacilityOverview of European Experience with Thorium FuelsConsideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated WaterTransmutation Half-LifeDevelopment of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 x 9 FuelDependence of Sensitivities on Numbers of Energy GroupsRBWR-TB2Measurement Activities by the Activation MethodSetup of the Calculation for 137CsSensitivity AnalysesResult of One-Batch CoreThe MYRRHA AcceleratorScenario AnalysisVI 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 AccidentSurface Wettability Change by IrradiationAccelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)OverviewRBWR SystemII Development of ADS Technologies: Current Status of Accelerator-Driven System DevelopmentIssues and Measures Against the Uranium-Free TRU Metallic Fast Reactor CoreRequirements for an Inventory List and Online Waste Management SystemExperimental SetupCriticality Characteristics of Fuel DebrisMA Transmutation Core ConceptIII Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material EngineeringRelated Technologies for ADS and Other Advanced Reactor SystemsRequirements for Long-Term Knowledge ManagementConsidering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom DebateMeasurement TechniquesRBWR-ACRBWR-TBOptions of Principles of Fuel Debris Criticality Control in Fukushima Daiichi ReactorsBubble-Induced TurbulenceIX Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear WastesEnhancement of Transmutation of Minor Actinides by Hydride TargetUranium-Loaded ADS ExperimentsCalculation MethodScenario AnalysisTh-MOX Fuels Irradiated in LWR ConditionsContact Angle MeasurementResults of Sensitivity AnalysesMeasurement Activities at J-PARC/MLF/ANNRIDevelopment of a γ-Ray Spectrometer for NRCA/PGAVII Nuclear Fuel Cycle Policy and Technologies: National Policy, Current Status, Future Prospects and Public Acceptance of the Nuclear Fuel Cycle Including Geological DisposalSpecification Selected for Uranium-Free TRU Metallic CoreDesign of Spallation Target for TEF-TPrevention of Severe ConsequenceDevelopment of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Application of a Self-Indication MethodFormation of an R&D Implementation and Evaluation TeamNuclear Transmutation of 137Cs with Laser Compton ScatteringOptions of Criticality Control PrinciplesReference ADS (MA-ADS)License Application and Schedule of the STACY ModificationResults and DiscussionExpectation for Nuclear TransmutationAnalysis and Discussion of Neutron FluxThe Situation NowReduction of Prediction UncertaintySeparation Using Anion-SRTransmutation CalculationNumerical Results and DiscussionSetting a Moratorium Period by “Temporal Safe Storage”Background and ObjectivesFuture PlansADS Design for Pu TransmutationThe Research and Development of Nuclear Technologies for Reactor Decommissioning, Safety Technology, Back-end, etc., Must Be Promoted Intensively Through International CooperationAssumption of Pu FeedPresent Condition of 1FNPS Fuel DebrisPartitioning of 14C into Solid, Liquid, and Gas PhasesMA Transmutation RateUranium-Loaded ADS ExperimentsVIII Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the Environment Monitored After the Accidents at TEPCO's Nuclear Power StationsResult of LWR-PuT“Management of the Total Amount” of HLWA Rough Draft of an NRD FacilityDeveloped Uranium-Free TRU Metallic CoreEffect of Boiling Heat Transfer on Surface WettabilityTechnology for the Back-end of the Nuclear Fuel Cycle Must Be Enhanced. The Site for Final Disposal of Nuclear Wastes Must be Determined as SoonResults and DiscussionComparison of Interfacial Area Concentration
 
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