Nuclear Back-End and Transmutation Technology for Waste Disposal : : Beyond the Fukushima Accident.

Nuclear Back-End and Transmutation Technology for Waste Disposal : : Beyond the Fukushima Accident.

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Bibliographic Details
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Nakajima, Ken.
Place / Publishing House:Tokyo : : Springer Japan,, 2014.
©2015.
Year of Publication:2014
Edition:1st ed.
Language:English
Online Access:
Physical Description:1 online resource (331 pages)
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Table of Contents:
  • Intro
  • Foreword
  • Preface
  • Cooperators
  • Contents
  • Part 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
  • Chapter 1: Nuclear Transmutation of Long-Lived Nuclides with Laser Compton Scattering: Quantitative Analysis by Theoretical Ap...
  • 1.1 Introduction
  • 1.2 Calculation Method
  • 1.2.1 Reaction via Giant Dipole Resonance
  • 1.2.2 High-Energy Photons Obtained by Laser Compton Scattering
  • 1.2.3 Setup of the Calculation for 137Cs
  • 1.3 Results and Discussion
  • 1.3.1 Nuclear Transmutation of 137Cs with Laser Compton Scattering
  • 1.3.2 Comparison with Other Nuclides
  • 1.4 Conclusion
  • References
  • Chapter 2: Recent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear M...
  • 2.1 Introduction
  • 2.2 Neutron Resonance Densitometry
  • 2.2.1 The Concept of NRD
  • 2.2.2 A Rough Draft of an NRD Facility
  • 2.3 Development of a gamma-Ray Spectrometer for NRCA/PGA
  • 2.4 Experiments for NRD Developments
  • 2.5 Summary
  • References
  • Chapter 3: Development of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Ap...
  • 3.1 Introduction
  • 3.2 Experiment
  • 3.3 Results and Discussion
  • 3.4 Summary
  • References
  • Chapter 4: Development of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Appli...
  • 4.1 Introduction
  • 4.2 Calculational Model and Condition
  • 4.3 Numerical Results and Discussion
  • 4.4 Conclusion
  • References
  • Chapter 5: Precise Measurements of Neutron Capture Cross Sections for LLFPs and MAs
  • 5.1 Introduction
  • 5.2 Present Situation of Data for LLFPs and MAs
  • 5.3 Measurement Activities by the Activation Method.
  • 5.4 Measurement Activities at J-PARC/MLF/ANNRI
  • 5.5 Summary
  • References
  • Chapter 6: Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9x9 Fuel
  • 6.1 Introduction
  • 6.2 Analytical Procedure
  • 6.3 Future Plans
  • 6.4 Conclusion
  • References
  • Part II: Development of ADS Technologies: Current Status of Accelerator-Driven System Development
  • Chapter 7: Contribution of the European Commission to a European Strategy for HLW Management Through Partitioning and Transmut...
  • 7.1 Introduction
  • 7.2 MYRRHA: A Flexible Fast-Spectrum Irradiation Facility
  • 7.3 The MYRRHA Accelerator
  • 7.4 Design of the Core and Primary System
  • 7.5 MYRRHA, A Research Tool in Support of the European Roadmap for PandT
  • 7.6 Conclusions
  • References
  • Chapter 8: Design of J-PARC Transmutation Experimental Facility
  • 8.1 Introduction
  • 8.2 Outline of the Transmutation Experimental Facility
  • 8.2.1 Outline of TEF-T
  • 8.2.2 Outline of TEF-P
  • 8.3 Design of Spallation Target for TEF-T
  • 8.4 Conclusion
  • References
  • Chapter 9: Accelerator-Driven System (ADS) Study in Kyoto University Research Reactor Institute (KURRI)
  • 9.1 Introduction
  • 9.2 Experimental Settings
  • 9.2.1 Uranium-Loaded ADS Experiments
  • 9.2.2 Thorium-Loaded ADS Benchmarks
  • 9.3 Results and Discussion
  • 9.3.1 Uranium-Loaded ADS Experiments
  • 9.3.1.1 Static Experiments
  • 9.3.1.2 Kinetic Experiments
  • 9.3.2 Thorium-Loaded ADS Experiments
  • 9.3.2.1 Static Experiments
  • 9.3.2.2 Kinetic Experiments
  • 9.4 Conclusions
  • References
  • Part III: Mechanical and Material Technologies for ADS: Development of Mechanical Engineering or Material Engineering- Related Technologies for ADS and Other Advanced Reactor Systems.
  • Chapter 10: Heat Transfer Study for ADS Solid Target: Surface Wettability and Its Effect on a Boiling Heat Transfer
  • 10.1 Introduction
  • 10.2 Surface Wettability Change by Irradiation
  • 10.2.1 Sample and Irradiation Facility
  • 10.2.1.1 Ultraviolet
  • 10.2.1.2 Gamma Rays (gamma-Rays)
  • 10.2.1.3 Proton Beam
  • 10.2.2 Contact Angle Measurement
  • 10.2.3 Effect of Irradiations on Surface Wettability
  • 10.3 Effect of Boiling Heat Transfer on Surface Wettability
  • 10.3.1 Experimental Setup and Procedure
  • 10.3.2 Results and Discussion
  • 10.4 Conclusions
  • References
  • Chapter 11: Experimental Study of Flow Structure and Turbulent Characteristics in Lead-Bismuth Two-Phase Flow
  • 11.1 Introduction
  • 11.2 Measurement Techniques
  • 11.2.1 Four-Sensor Probe
  • 11.2.2 Electromagnetic Probe
  • 11.3 Experimental Setup
  • 11.4 Results and Discussion
  • 11.4.1 Radial Profiles of Two-Phase Flow Properties
  • 11.4.2 Comparison of Interfacial Area Concentration
  • 11.4.3 Bubble-Induced Turbulence
  • 11.5 Conclusions
  • References
  • Part IV: Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADS
  • Chapter 12: Theory of Power Spectral Density and Feynman-Alpha Method in Accelerator-Driven System and Their Higher-Order Mode...
  • 12.1 Introduction
  • 12.2 Theory of Feynman-α Method in ADS
  • 12.3 Theory of Power Spectral Density in ADS
  • 12.4 Conclusions
  • References
  • Chapter 13: Study on Neutron Spectrum of Pulsed Neutron Reactor
  • 13.1 Introduction
  • 13.2 Experiment at KUCA and Measured Results
  • 13.3 Analysis and Discussion of Neutron Flux
  • 13.3.1 Neutron Flux Distribution
  • 13.3.2 Neutron Spectrum
  • 13.4 Conclusions
  • References
  • Part V: Next-Generation Reactor Systems: Development of New Reactor Concepts of LWR or FBR for the Next-Generation Nuclear Fuel Cycle.
  • Chapter 14: Application of the Resource-Renewable Boiling Water Reactor for TRU Management and Long-Term Energy Supply
  • 14.1 Introduction
  • 14.2 RBWR System
  • 14.2.1 Overview
  • 14.2.2 Core Calculation Method
  • 14.2.3 RBWR-AC
  • 14.2.4 RBWR-TB
  • 14.2.5 RBWR-TB2
  • 14.3 Conclusion
  • References
  • Chapter 15: Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core
  • 15.1 Introduction
  • 15.2 Issues and Measures Against the Uranium-Free TRU Metallic Fast Reactor Core
  • 15.3 Parametric Analysis on the Effect of Measures
  • 15.3.1 Parametric Analysis Methodology
  • 15.3.2 Analysis Results for Doppler Feedback Enhancement
  • 15.3.3 Analysis Results for Burnup Reactivity Swing Reduction
  • 15.4 Developed Uranium-Free TRU Metallic Core
  • 15.4.1 Specification Selected for Uranium-Free TRU Metallic Core
  • 15.4.2 Performance of the Uranium-Free TRU Metallic Core
  • 15.5 Conclusions
  • References
  • Chapter 16: Enhancement of Transmutation of Minor Actinides by Hydride Target
  • 16.1 Introduction
  • 16.2 Design of MA-Hydride Target
  • 16.3 Design of Core with MA-Hydride Target
  • 16.4 Transmutation Calculation
  • 16.5 Discussion
  • 16.6 Conclusions
  • References
  • Chapter 17: Method Development for Calculating Minor Actinide Transmutation in a Fast Reactor
  • 17.1 Introduction
  • 17.2 MA Transmutation Core Concept
  • 17.3 MA Transmutation Rate
  • 17.4 Sensitivity Calculation Method
  • 17.4.1 Sensitivity to Infinite-Dilution Cross Section
  • 17.4.2 Burn-up Sensitivity
  • 17.4.3 Dependence of Sensitivities on Numbers of Energy Groups
  • 17.5 Reduction of Prediction Uncertainty
  • 17.6 Conclusion
  • References
  • Chapter 18: Overview of European Experience with Thorium Fuels
  • 18.1 Introduction
  • 18.2 Thorium European Research Programme History
  • 18.3 Th-MOX Fuels Irradiated in LWR Conditions
  • 18.4 The Molten Salt Reactor.
  • 18.5 Conclusions
  • References
  • Part 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
  • Chapter 19: Transmutation Scenarios after Closing Nuclear Power Plants
  • 19.1 Introduction
  • 19.2 Methodology
  • 19.2.1 Neutronics Calculation
  • 19.2.2 Scenario Analysis
  • 19.2.3 Transmutation Half-Life
  • 19.3 ADS Design for Pu Transmutation
  • 19.3.1 Reference ADS (MA-ADS)
  • 19.3.2 Assumption of Pu Feed
  • 19.3.3 Result of One-Batch Core
  • 19.3.4 Result of six-Batch Core
  • 19.4 Scenario Analysis
  • 19.4.1 Result of LWR-OT
  • 19.4.2 Result of LWR-PuT
  • 19.4.3 Result of FR
  • 19.4.4 Result of ADS
  • 19.4.5 Result of FR+ADS
  • 19.4.6 Impact on the Repository
  • 19.4.7 Discussion
  • 19.5 Conclusion
  • Nomenclature
  • References
  • Chapter 20: Sensitivity Analyses of Initial Compositions and Cross Sections for Activation Products of In-Core Structure Mater...
  • 20.1 Introduction
  • 20.2 Method of Calculating Sensitivity Coefficients
  • 20.3 Sensitivity Analyses
  • 20.3.1 Analyses Conditions
  • 20.3.2 Target Nuclides of Sensitivity Analyses
  • 20.3.3 Results of Sensitivity Analyses
  • 20.3.4 Sensitivity Analysis Using the Initial Composition Based on Measured Data
  • 20.4 Conclusion
  • References
  • Chapter 21: Options of Principles of Fuel Debris Criticality Control in Fukushima Daiichi Reactors
  • 21.1 Introduction
  • 21.2 Present Condition of 1FNPS Fuel Debris
  • 21.3 Criticality Characteristics of Fuel Debris
  • 21.4 Options of Criticality Control Principles
  • 21.4.1 Prevention of Criticality by Poison or Dry Process
  • 21.4.2 Prevention of Criticality by Monitoring
  • 21.4.3 Prevention of Severe Consequence
  • 21.4.4 Risk Assessment
  • 21.5 Conclusions
  • References.
  • Chapter 22: Modification of the STACY Critical Facility for Experimental Study on Fuel Debris Criticality Control.

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