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

ExperimentalIV Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADSNuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical ApproachThe Molten Salt ReactorADS Design for Pu TransmutationCombustion MethodBubble-Induced TurbulenceCombustion MethodAnalysis Results for Doppler Feedback EnhancementCore Calculation MethodTarget Nuclides of Sensitivity AnalysesDiscussionThe MYRRHA AcceleratorPrevention of Criticality by MonitoringOverviewExperiment at KUCA and Measured ResultsThorium-Loaded ADS ExperimentsDeveloped Uranium-Free TRU Metallic CoreMethod Development for Calculating Minor Actinide Transmutation in a Fast ReactorEnhancement of Transmutation of Minor Actinides by Hydride TargetFuture PlansIX Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear WastesOutline of TEF-TDesign of MA-Hydride TargetGlobal Warming Is Becoming a More Serious ProblemPrinciple of Ferrocyanide Coprecipitation for Cs RemovalResults and DiscussionRequirements for an Inventory List and Online Waste Management SystemOutline of the CoursesResults and DiscussionA Rough Draft of an NRD FacilityVIII Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the Environment Monitored After the Accidents at TEPCO's Nuclear Power StationsExpectation for Nuclear TransmutationBehavior of 14C in Rice Paddy FieldsVI 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 AccidentSensitivity to Infinite-Dilution Cross SectionRadial Profiles of Two-Phase Flow PropertiesRisk AssessmentScenario AnalysisVolume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation TechniqueReduction of Prediction UncertaintyApplication of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy SupplyModification of STACYResearch and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage the Progress of Final DisposalRequirements for Long-Term Knowledge ManagementDifficulty in Site SelectionImpact on the RepositoryNumerical Results and DiscussionResults and DiscussionResult of FR+ADSMA Transmutation Core ConceptAccelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)Nuclear Transmutation of 137Cs with Laser Compton ScatteringPartitioning of 14C into Solid, Liquid, and Gas PhasesOptions of Criticality Control PrinciplesExperimental SetupMeasurement Activities by the Activation MethodManufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]MYRRHA: A Flexible Fast-Spectrum Irradiation FacilityOptions of Principles of Fuel Debris Criticality Control in Fukushima Daiichi ReactorsMA Transmutation RateHuman Beings Cannot Avoid Depending on Nuclear Energy as Well as Other Energy Resources, Including Renewable Energy, Which Do Not Emit CO2Awareness of the Limits of Scientific and Technical AbilitiesParametric Analysis MethodologyResults of Sensitivity AnalysesII Development of ADS Technologies: Current Status of Accelerator-Driven System DevelopmentBurn-up SensitivityExperimentalMeasurement TechniquesOutline of the Transmutation Experimental FacilityWhy has Such a Situation Occurred?RBWR-TB2Neutron Flux DistributionPrecise Measurements of Neutron Capture Cross Sections for LLFPs and MAsCalculational Model and ConditionDevelopment Strategy of Waste Treatment, Storage, Transport, and Disposal TechnologiesNeutron SpectrumDependence of Sensitivities on Numbers of Energy GroupsRBWR-ACTransmutation CalculationDevelopment of a γ-Ray Spectrometer for NRCA/PGAIssues and Measures Against the Uranium-Free TRU Metallic Fast Reactor CoreResult of One-Batch CorePresent Condition of 1FNPS Fuel DebrisMethodologyOverview of European Experience with Thorium FuelsTransmutation Half-LifeNeutron Resonance DensitometryLicense Application and Schedule of the STACY ModificationNotesThe Concept of NRDReaction via Giant Dipole ResonanceModification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality ControlNuclear Technology Must be DevelopedResults and DiscussionRBWR-TBEnvironmental Transfer of Carbon-14 in Japanese Paddy FieldsSensitivity Calculation MethodConcept of Geological Disposal and RiskReagentsEffect of Boiling Heat Transfer on Surface WettabilityReference ADS (MA-ADS)Design of the Core and Primary SystemSample and Irradiation FacilityDesign of J-PARC Transmutation Experimental FacilityAnalysis Results for Burnup Reactivity Swing ReductionInvolvement of Microorganisms in the 14C BehaviorCalculation MethodContribution of the European Commission to a European Strategy for HLW Management Through Partitioning & TransmutationIII Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material EngineeringRelated Technologies for ADS and Other Advanced Reactor SystemsResult of LWR-PuTV Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel CycleTh-MOX Fuels Irradiated in LWR ConditionsRecent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear Materials in Particle-Like DebrisResults and DiscussionContact Angle MeasurementReflections on the CoursesAnalyses ConditionsResult of six-Batch CoreResult of FRIssues for the FutureHeat Transfer Study for ADS Solid Target:Presentation of MYRRHA and Its Role in the European P&T StrategyExperimental Study on Criticality Control for Fuel DebrisDevelopment of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Application of a Self-Indication MethodSensitivity Analysis Using the Initial Composition Based on Measured DataResults and DiscussionUranium-Loaded ADS ExperimentsTransfer of 14C from Soil to Rice PlantsDevelopment of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 x 9 FuelResult of LWR-OTCritical Experiments on Criticality Safety for Fuel DebrisPresent Situation of Data for LLFPs and MAsCurrent Status of HLWDiscussionUranium-Loaded ADS ExperimentsRBWR SystemHLW Disposal Program in JapanDevelopment of Uranium-Free TRU Metallic Fuel Fast Reactor CoreParametric Analysis on the Effect of MeasuresThe Research and Development of Nuclear Technologies for Reactor Decommissioning, Safety Technology, Back-end, etc., Must Be Promoted Intensively Through International CooperationSurface Wettability Change by IrradiationDesign of Spallation Target for TEF-TAnalysis and Discussion of Neutron FluxPrevention of Criticality by Poison or Dry ProcessConcerns on HLWTheory of Power Spectral Density and Feynman-Alpha Method in AcceleratorDriven System and Their Higher-Order Mode EffectsSensitivity AnalysesDemand for Primary Energy and Electricity Is Increasing Year by YearSpecification Selected for Uranium-Free TRU Metallic CoreI 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 DataAssumption of Pu FeedConsidering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom Debate“Management of the Total Amount” of HLWDeciding the TopicSetting a Moratorium Period by “Temporal Safe Storage”Method of Calculating Sensitivity CoefficientsVII Nuclear Fuel Cycle Policy and Technologies: National Policy, Current Status, Future Prospects and Public Acceptance of the Nuclear Fuel Cycle Including Geological DisposalStudy on Neutron Spectrum of Pulsed Neutron ReactorTransmutation Scenarios after Closing Nuclear Power PlantsResults of the Questionnaire SurveyTheory of Feynman-α Method in ADSExperimentPrevention of Severe ConsequenceSafety Technology of Nuclear Energy Must Be Developed for the FutureCriticality Characteristics of Fuel DebrisScenario AnalysisIssues of HLW Disposal in JapanThorium European Research Programme HistoryResearch MethodExperimental Study of Flow Structure and Turbulent Characteristics in Lead– Bismuth Two-Phase FlowSeparation Using Anion-SRTheory of Power Spectral Density in ADSExperimental SettingsComparison with Other NuclidesExperiments for NRD DevelopmentsSetup of the Calculation for 137CsThe Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and BudgetTechnology for the Back-end of the Nuclear Fuel Cycle Must Be Enhanced. The Site for Final Disposal of Nuclear Wastes Must be Determined as SoonThorium-Loaded ADS BenchmarksFour-Sensor ProbeEffect of Irradiations on Surface WettabilityElectromagnetic ProbeDevelopment of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daiichi Nuclear Power StationSix Proposals by the Science Council of JapanFormation of an R&D Implementation and Evaluation TeamResults and DiscussionMeasurement Activities at J-PARC/MLF/ANNRIBackground and ObjectivesHigh-Energy Photons Obtained by Laser Compton ScatteringNeutronics CalculationMYRRHA, A Research Tool in Support of the European Roadmap for P&TPerformance of the Uranium-Free TRU Metallic CoreExperimental Setup and ProcedureAnalytical ProcedureConsideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated WaterOutline of TEF-PDesign of Core with MA-Hydride TargetResult of ADSSensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure MaterialsThe Situation NowDevelopment of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Application of a Self-Indication MethodSeparation Using Anion-SRComparison of Interfacial Area Concentration
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