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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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