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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 Analyses IV Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADS Analysis Results for Doppler Feedback Enhancement Analysis Results for Burnup Reactivity Swing Reduction Result of ADS Heat Transfer Study for ADS Solid Target:Development Strategy of Waste Treatment, Storage, Transport, and Disposal Technologies Neutron Spectrum Behavior of 14C in Rice Paddy Fields Outline of TEF-P Results and Discussion Prevention of Criticality by Monitoring Nuclear Technology Must be Developed Theory of Feynman-α Method in ADS Experimental Setup and Procedure Neutron Resonance Densitometry Issues for the Future V Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel Cycle Present Situation of Data for LLFPs and MAs Awareness of the Limits of Scientific and Technical Abilities High-Energy Photons Obtained by Laser Compton Scattering Concerns on HLW Concept of Geological Disposal and Risk Experimental Study on Criticality Control for Fuel Debris Results of the Questionnaire Survey Demand for Primary Energy and Electricity Is Increasing Year by Year Methodology Radial Profiles of Two-Phase Flow Properties Thorium European Research Programme History Study on Neutron Spectrum of Pulsed Neutron Reactor Environmental Transfer of Carbon-14 in Japanese Paddy Fields Electromagnetic Probe Results and Discussion Result of LWR-OT Experimental Study of Flow Structure and Turbulent Characteristics in Lead– Bismuth Two-Phase Flow Deciding the Topic Effect of Irradiations on Surface Wettability Design of J-PARC Transmutation Experimental Facility Development of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daiichi Nuclear Power Station Performance of the Uranium-Free TRU Metallic Core Reflections on the Courses Thorium-Loaded ADS Benchmarks Recent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear Materials in Particle-Like Debris Analyses Conditions Method of Calculating Sensitivity Coefficients Design of the Core and Primary System Result of FR Result of six-Batch Core Global Warming Is Becoming a More Serious Problem Combustion Method Involvement of Microorganisms in the 14C Behavior MYRRHA: A Flexible Fast-Spectrum Irradiation Facility Result of FR+ADS Parametric Analysis Methodology Development of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Application of a Self-Indication Method Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Materials Experimental Analytical Procedure Sample and Irradiation Facility Design of MA-Hydride Target Six Proposals by the Science Council of Japan Comparison with Other Nuclides Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core Experiments for NRD Developments Nuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical Approach Separation Using Anion-SR The Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and Budget Human Beings Cannot Avoid Depending on Nuclear Energy as Well as Other Energy Resources, Including Renewable Energy, Which Do Not Emit CO2 Method Development for Calculating Minor Actinide Transmutation in a Fast Reactor Results and Discussion Sensitivity to Infinite-Dilution Cross Section Safety Technology of Nuclear Energy Must Be Developed for the Future Issues of HLW Disposal in Japan Outline of TEF-T Results and Discussion I 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 Data Experiment at KUCA and Measured Results Thorium-Loaded ADS Experiments Neutronics Calculation Experiment Burn-up Sensitivity Notes Precise Measurements of Neutron Capture Cross Sections for LLFPs and MAs Outline of the Courses Transmutation Scenarios after Closing Nuclear Power Plants Research and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage the Progress of Final Disposal Modification of STACY Current Status of HLW Sensitivity Analysis Using the Initial Composition Based on Measured Data Principle of Ferrocyanide Coprecipitation for Cs Removal Modification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality Control Why has Such a Situation Occurred?The Concept of NRD Difficulty in Site Selection MYRRHA, A Research Tool in Support of the European Roadmap for P&T Application of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy Supply Reaction via Giant Dipole Resonance Research Method Discussion Prevention of Criticality by Poison or Dry Process Calculational Model and Condition Core Calculation Method Design of Core with MA-Hydride Target Manufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]Experimental Combustion Method Theory of Power Spectral Density and Feynman-Alpha Method in AcceleratorDriven System and Their Higher-Order Mode Effects Risk Assessment Theory of Power Spectral Density in ADS Volume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation Technique Discussion Presentation of MYRRHA and Its Role in the European P&T Strategy Four-Sensor Probe Results and Discussion Parametric Analysis on the Effect of Measures Impact on the Repository Transfer of 14C from Soil to Rice Plants Contribution of the European Commission to a European Strategy for HLW Management Through Partitioning & Transmutation The Molten Salt Reactor HLW Disposal Program in Japan Critical Experiments on Criticality Safety for Fuel Debris Neutron Flux Distribution Sensitivity Calculation Method Experimental Settings Reagents Outline of the Transmutation Experimental Facility Overview of European Experience with Thorium Fuels Consideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated Water Transmutation Half-Life Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9 x 9 Fuel Dependence of Sensitivities on Numbers of Energy Groups RBWR-TB2 Measurement Activities by the Activation Method Setup of the Calculation for 137Cs Sensitivity Analyses Result of One-Batch Core The MYRRHA Accelerator Scenario Analysis 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 Accident Surface Wettability Change by Irradiation Accelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)Overview RBWR System II Development of ADS Technologies: Current Status of Accelerator-Driven System Development Issues and Measures Against the Uranium-Free TRU Metallic Fast Reactor Core Requirements for an Inventory List and Online Waste Management System Experimental Setup Criticality Characteristics of Fuel Debris MA Transmutation Core Concept III Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material EngineeringRelated Technologies for ADS and Other Advanced Reactor Systems Requirements for Long-Term Knowledge Management Considering the Geological Disposal Program of High-Level Radioactive Waste Through Classroom Debate Measurement Techniques RBWR-AC RBWR-TB Options of Principles of Fuel Debris Criticality Control in Fukushima Daiichi Reactors Bubble-Induced Turbulence IX Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear Wastes Enhancement of Transmutation of Minor Actinides by Hydride Target Uranium-Loaded ADS Experiments Calculation Method Scenario Analysis Th-MOX Fuels Irradiated in LWR Conditions Contact Angle Measurement Results of Sensitivity Analyses Measurement Activities at J-PARC/MLF/ANNRI Development of a γ-Ray Spectrometer for NRCA/PGA VII Nuclear Fuel Cycle Policy and Technologies: National Policy, Current Status, Future Prospects and Public Acceptance of the Nuclear Fuel Cycle Including Geological Disposal Specification Selected for Uranium-Free TRU Metallic Core Design of Spallation Target for TEF-T Prevention of Severe Consequence Development of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Application of a Self-Indication Method Formation of an R&D Implementation and Evaluation Team Nuclear Transmutation of 137Cs with Laser Compton Scattering Options of Criticality Control Principles Reference ADS (MA-ADS)License Application and Schedule of the STACY Modification Results and Discussion Expectation for Nuclear Transmutation Analysis and Discussion of Neutron Flux The Situation Now Reduction of Prediction Uncertainty Separation Using Anion-SR Transmutation Calculation Numerical Results and Discussion Setting a Moratorium Period by “Temporal Safe Storage”Background and Objectives Future Plans ADS Design for Pu Transmutation The Research and Development of Nuclear Technologies for Reactor Decommissioning, Safety Technology, Back-end, etc., Must Be Promoted Intensively Through International Cooperation Assumption of Pu Feed Present Condition of 1FNPS Fuel Debris Partitioning of 14C into Solid, Liquid, and Gas Phases MA Transmutation Rate Uranium-Loaded ADS Experiments VIII Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the Environment Monitored After the Accidents at TEPCO's Nuclear Power Stations Result of LWR-PuT “Management of the Total Amount” of HLW A Rough Draft of an NRD Facility Developed Uranium-Free TRU Metallic Core Effect of Boiling Heat Transfer on Surface Wettability Technology for the Back-end of the Nuclear Fuel Cycle Must Be Enhanced. The Site for Final Disposal of Nuclear Wastes Must be Determined as Soon Results and Discussion Comparison of Interfacial Area Concentration

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