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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»

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

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