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Nuclear Back-end and Transmutation Technology for Waste Disposal

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Nuclear Back-end and Transmutation Technology for Waste Disposal

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

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