1. 1-1 Development of a Neutron Detector with Improved Heat Resistance
    －Consideration of the Thermal Cycle Load Specific to High Temperature Gas-Cooled Reactors－
  2. 1-2 Toward the Demonstration of H2 Production Technology Using the HTGR
    －Development of Safety Design Philosophy for HTTR Heat Application Test Facility－
  3. 1-3 Evaluation of the Fuel Integrity of High Temperature Gas-Cooled Reactor to Maximize the Performance
    －Improvement of the Failure Assessment Method of Tristructural Isotropic Fuel Performance for High Temperature Gas-Cooled Reactor－
  4. 1-4 Feasibility Study on Reprocessing Technology of HTGR Spent Fuel
    －Improving the Economics of Reprocessing Based on the Existing PUREX Technology－
  5. 1-5 Toward Stable Hydrogen Production by the IS Process
    －Development of a Composition Control Method to Prevent Pipe Clogging by Iodine Precipitation－
  6. 1-6 Energy Saving for H2 Production by the IS Process
    －Membrane Development for HI Concentration to Suppress Swelling by Cross-Linking－
  7. 1-7 Enhancement of Corrosion Resistance of the Metallic Components Used in the IS Process
    －Exploring a Coating Material That Can Withstand a Sulfuric Acid Boiling Environment－
  1. 2-1 Measures Against Beyond Design-Basis Accidents to Effectively Reduce Accidents Possibly Involving Core Damage
    －Probabilistic Risk Assessment Results for Fast Reactor Operational Conditions－
  2. 2-2 In-Vessel Retention of Molten Core Materials
    －Visualization Experiment of Molten Core Materials Penetrating into Liquid Sodium－
  3. 2-3 Prediction of Whole-Plant Thermal-Hydraulic Performance in Sodium-Cooled Fast Reactors
    －Coupling of One-Dimensional Plant Dynamics Analysis and Three-Dimensional Detailed Analysis Codes－
  4. 2-4 Feasibility Study of Application of Dissimilar Welding Technology to Fast-Reactor Wrapper Tubes
    －Applicability to Fast-Reactor Core Revealed by Microstructural Analysis－
  5. 2-5 Toward an Efficient Shielding Design of Fast Reactors
    －Evaluation of Sodium Radioactivity in the Primary System of the Prototype Fast Reactor Monju－
  1. 3-1 Establishment of a γ-Ray-Spectroscopy Technique to Study Actinide Nuclei
    －Advancing Research on the Nuclear Structure of Superheavy Elements－
  2. 3-2 Uncovering the Origin of Short-Range Repulsive Nuclear Force Produced by Quarks
    －Σ+p Scattering Experiment at J-PARC－
  3. 3-3 Successful Growth of High-Quality Uranium-Based Superconducting Crystals
    －Contributing to the Elucidation of the Mechanism of Uranium-Based Superconductivity－
  4. 3-4 Toward Highly Sensitive Detection of Sound Waves
    －Sound Waves Drastically Alter Current−Voltage Characteristics－
  5. 3-5 Why Can One Atomic Layer Graphene Separate Hydrogen and Deuterium?
    －Toward the Mass Production of Deuterium Based on Quantum Tunneling－
  6. 3-6 Development of a New, Multilayered Electrode for Tunnel Magnetoresistance Devices with High-Performance and Functionality
    －New Tunnel Magnetoresistance Devices for Advanced Industrial Applications－
  7. 3-7 Mysterious Energy Hidden in Thin Magnets
    －Theory of Energy Generation in Extremely Small Systems－
  1. 4-1 Development of a Nondestructive Analysis System for Nuclear Material Measurement by Active Methods
    －World’s First System Capable of Conducting Three Nondestructive Measurements－
  2. 4-2 Foundational Database for Diversifying Needs
    －Development of the Latest Nuclear Data Library JENDL-5－
  3. 4-3 Toward High Recovery Yields of Pyrochemical Reprocessing for Minor Actinide Transmutation Nitride Fuels
    －Chlorination of Neptunium in Platinum Group Elements Compounds Without Using Corrosive Gases－
  4. 4-4 Development of a New Corrosion Inhibition Method Using Chelation Technique
    －Crevice Corrosion Suppression by EDTA-Based Metal-Ion Introduction－
  5. 4-5 Computational Design of High-Strength Alloys
    －Element Strategy Alloy-Design via Electronic Structure Calculations－
  6. 4-6 Mechanism of Actinide Transfer Between Water and Oil
    －Studies of the Molecular Structure of Solvent Extraction Interfaces Using Vibrational Sum Frequency Generation Spectroscopy－
  7. 4-7 Development of a System for Whole-Body Dose Assessment in Carbon Ion Radiotherapy
    －Use of Past Experience in Carbon Ion Radiotherapy to the Future of Radiotherapy－
  8. 4-8 Measuring Neutrons Emitted in Spallation Reactions
    －Toward Improving Prediction Accuracy Using Nuclear Reaction Models－
  1. 5-1 Beam Loss Assessment of High-Intensity Negative Hydrogen Ion Beams
    －Observation of Neutral Beams Generated by Residual Gas Electron Stripping－
  2. 5-2 Inelastic Neutron Scattering Experiments Under the Highest Pressure in the World
    －Observation of Hydrogen Vibrational Excitation of Metal Hydrides at 21 GPa－
  3. 5-3 Neutron Diffraction Experiments Under Pulsed High Magnetic Fields
    －Development of a High-Field Pulsed Magnet System Exceeding 30 T－
  4. 5-4 Neutron Scattering Measurements for Magnetic Moment in Comparison with Nuclear Spin Polarization
    －A New Technique Useful in Study on Magnetism and Material－
  5. 5-5 Visualizing Lithium-Ion Transfer in All-Solid-State Batteries
    －Neutron Depth Profiling for the Operand Measurement of Li Ions－
  6. 5-6 Demonstration of Laser-Assisted Separation of Actinides
    －Enhancing Selectivity in Solvent Extraction by Manipulating f Electrons with Light－
  7. 5-7 Growth Process of Silicon Oxide Films Revealed Using High-Brightness Synchrotron Radiation
    －Interfacial Defects and Carrier Trapping Dominate the World of Nanodevices－
  1. 6-1 Can Machine Learning Predict the Atomic Motion Inside Nuclear Fuel Materials?
    －Toward the Application of Machine-Learning Molecular Dynamics to Nuclear Fuel Materials－
  2. 6-2 Specificity of Liquid Metal Embrittlement
    －Energy Criteria for Embrittlement: Atomistic Weak Interactions－
  3. 6-3 Understanding Hydrated Radium at the Molecular Level
    －The Advent of Molecular-Level Research on Radium 125 Years After the Discovery of the Element－
  4. 6-4 Exploring Large-Scale Simulations in Virtual Space
    －Making Interactive Remote Virtual Reality Visualization Possible－
  5. 6-5 New Data Conversion Method to Accelerate Nuclear Simulation
    －Matrix Solvers with 16-Bit Operations Achieve Same Convergence as 64-Bit Operations－
  1. 7-1 Prevention of Acts of Nuclear/Radiation Terrorism at Large Public Events
    －Development of Detection Equipment to Estimate the Direction of Incoming Neutrons－
  1. 8-1 Lessons Learned from the Chornobyl Nuclear Power Plant
    －What is the Condition Needed to Suppress Degradation of Fuel Debris?－
  2. 8-2 Radiation Emitted from Fuel Debris
    －Elucidation of the Characteristics of Bremsstrahlung X-Rays and Effects of the Dose Rate－
  3. 8-3 Utilizing the Directivity of Cherenkov Radiation to Distinguish 90Sr/90Y and 137Cs
    －Simultaneous Detection of the Source Positions of 90Sr/90Y and 137Cs－
  4. 8-4 Automatic Discrimination of Structure Category in the Workspace
    －Development of a Structure Discrimination Method by Deep Learning Based on 3D Point Cloud－
  5. 8-5 Toward Predicting Cesium Distribution in FDNPS
    －Improvement of the Analysis Code of Cesium Behavior in a Severe Accident－
  6. 8-6 Toward Predicting the Properties of Cesium Remaining in FDNPS Reactor Buildings
    －Clarification of Cesium Adsorption on Nonferrous Structural Materials－
  7. 8-7 Toward the Safe Storage and Management of Wastes Such as Fuel Debris
    －Research and Development on Hydrogen Leakage/Diffusion Behavior Analysis－
  8. 8-8 Numerical Analysis of Hydrogen Combustion Behavior
    －Effects of Temperature and Pressure on Flame Instability－
  9. 8-9 Estimating Fuel Debris Temperature in FDNPS Unit 2 Under Air-Cooling Condition
    －Numerical Simulation of Fuel Debris Heat Transfer－
  10. 8-10 Effects of Forests on 137Cs Behavior in River Catchment
    －Development of a Watershed Model Combined with 137Cs Migration in a Forest－
  11. 8-11 Future Behavior of Radiocesium on Land
    －Prediction of Radiocesium Behavior on Land for 30 Years－
  12. 8-12 Remobilization Mechanism of Radiocesium from Bottom Sediments in Reservoir
    －Vertical Distribution of 137Cs in Sediment-Pore Water－
  13. 8-13 Observation of Radiocesium Behavior in Estuaries
    －Estimating the Origin of Particles Forming Turbid Layers near the Seabed－
  14. 8-14 Lichen as a Recorder of Radiocaesium
    －Determining Radiocaesium Distributions in Biological Tissues by Combining Analytical Equipment－
  15. 8-15 Toward the Rapid Analysis of Plutonium Isotopes
    －Analytical Technique Without Pretreatments－
  16. 8-16 Reviews on Exposure Management for Residents After the Accident in Fukushima
    －Toward the Lifting of Evacuation Orders for the Benefit of the Residents－
  1. 9-1 Direct Observation of Fractures to Estimate Future Permeability
    －Application of Fracture Visualization Technology by Resin Injection－
  2. 9-2 Deep Groundwater Physicochemical Components Affecting Actinide Migration
    －Addition of Trace Elements to Groundwater in Granite and Mudstone－
  3. 9-3 Estimating the Erosion History Around the Depth of Geological Disposal
    －Reconstructing Thermal History by Optically Stimulated Luminescence Thermochronometry of Borehole Cores－
  4. 9-4 Accelerator Mass Spectrometer: The Challenge of Ultra-Downsizing
    －Filtering Atoms and Molecules Using Crystal Surfaces－
  5. 9-5 Bentonite Swelling and Interlayer Cation Behavior
    －Why the Expandability of Montmorillonite is Different Between K+ and NH4+ in Bentonite?－
  6. 9-6 Evaluation of Radionuclide Migration by a Diffusion Model
    －Diffusion Test and Model Development for Compacted Ca-Bentonite－
  1. 10-1 Toward an Efficient Design for Disposal Facilities
    －Evaluation of Skyshine Dose Generated from Disposal Facilities－
  2. 10-2 Toward the Practical Application of Flame-Retardant Waste Treatment Test Equipment
    －Selection of Repair Materials for the Main Reactor Refractory－
  3. 10-3 Toward Using Geopolymer for the Treatment of Radioactive Wastes
    －Investigation on the Possible Pathway of Zeolites Formation in the Geopolymer－
  4. 10-4 Toward the Safe and Long-Term Storage of Plutonium
    －Aggregation of Plutonium and Shift to PVC-Free Storage－
  1. 11-1 Toward Rapid Inspection for Evacuation Vehicle Contamination in a Nuclear Emergency
    －Examination of the Performance of the Portal Monitor to Inspect Vehicles of Evacuees－
  2. 11-2 Clarifying Damage Conditions of Structures Subjected to Projectile Impact
    －Investigation of Damage Condition of Reinforced Concrete Panels Simulating Outer Walls of a Nuclear Building－
  3. 11-3 Toward Improving the Accuracy of the Structural Integrity Assessment Method for Reactor Pressure Vessels
    －Effect of Stainless-Steel Overlay Cladding on Fracture Behavior of the Reactor Pressure Vessel－
  4. 11-4 Toward More Rational Light Water Reactor Fuel Design and Safety Assessment
    －Establishing a Model to Predict Irradiation Growth in Zirconium-Based Alloy Claddings－
  5. 11-5 Confinement of Radioactive Materials Within the Facility Under Fire Conditions
    －Evaluation of the Properties of High-Efficiency Particulate Air Filters Clogged with Soot from Burned Gloveboxes－
  6. 11-6 Accurate Estimation of the Three-Dimensional Distribution of Groundwater Contamination
    －Expectation for Contribution to Understand Underground Contamination for Decommissioning－
  7. 11-7 Filtering Out Radioactive Materials from a Pool During Severe Accidents
    －Evaluation of Two-Phase Flow Behavior During Pool Scrubbing by Computational Fluid Dynamics Simulation－
  8. 11-8 Validation of the Latest Nuclear Data Library
    －Postirradiation Experiment Analysis of Pressurized Water Reactor Fuels Using JENDL-5－
  1. 1-1 Degradation of Fuel Debris Under the Effect of Ionizing Radiation
    －Formation of Solid Solution Improves Stability to Oxidative Degradation－
  2. 1-2 Criticality Evaluation of Fuel Debris with Unclear Material Composition
    －Development of a New Subcritical Depletion Code for Monitoring Noble Gases－
  3. 1-3 Clarifying the Failure Mechanism of the Lower Part of the RPV
    －Melting Test Assuming a Eutectic Reaction in the Complex Structure of a BWR－
  4. 1-4 How to Effectively Remove Iodate from Solutions?
    －Coprecipitation of Iodate with Barite (BaSO4) Was Evaluated at a Molecular Level－
  5. 1-5 Characterization of Radioactive Waste for Safe Storage
    －Effect on the Chemical Composition of Carbonate Slurry－
  6. 1-6 Realization of γ-Ray Nuclide Analysis Under Severe Radiation Fields
    －Development of a γ-Ray Spectrometry System Specific to High Dose Rates for Simple Nondestructive Assays－
  7. 1-7 In-situ Monitoring System for Radioactive Aerosols
    －Real-Time Monitoring of Alpha Aerosols to Improve Worker Safety－
  8. 1-8 Simultaneous Measurement of the Energy Spectra of Alpha, Beta, and Gamma Rays
    －Development of a Portable Continuous Air-Monitoring System for Detecting Alpha/Beta/Gamma Radioactive Material－
  9. 1-9 Novel Single-End Readout-Type Optical Fiber Radiation Sensor
    －Highly Sensitive Position Detection by Photon Wavelength Analysis Using a New Spectroscopy System－
  10. 1-10 Visualization of Radioactive Contamination at the Decommissioning Site on a Three-Dimensional Map
    －Understanding Invisible Radioactive Contamination in a Virtual Space and Reducing Worker Exposure－
  11. 1-11 Impact of Extreme Typhoons on Radiocesium Discharge
    －Comparison of Effects of Two Typhoons-Etau in 2015 and Hagibis in 2019－
  12. 1-12 Approaching the Secrets of Long-Term Cesium Retention in Lichen
    －Computational Chemistry Solves the Energetics of Complexation of Metabolites with Cesium－
  13. 1-13 Rapid Analysis for Long Half-Life 99Tc
    －ICP-MS Analysis with Solid-Phase Extraction and Gas-Phase Reaction－
  14. 1-14 Selective Detection of Trace Sr Isotopes Using Lasers
    －Simplified Pretreatment of Samples Containing Isobars and Stable Isotopes－
  15. 1-15 Toward Confident Hot-Spot Visualization Using an Unmanned Helicopter
    －Improvement of Detection Accuracy by Selecting Data on the Flight Conditions－
  16. 1-16 Research on the Decreasing Trend of Atmospheric Radiocesium Concentration After the Accident
    －Assessing the Decrease Rate Based on Governmental Monitoring Results－
  17. 1-17 Why Does the Air Dose Rate in Urban Areas Decline Quickly?
    －Reduction Effect Revealed by the Behavior of Radioactive Cesium－
  1. 2-1 Understanding Reactor Risk Profiles Against External Events
    －Probabilistic Assessment of Internal Flooding-Induced Risks by a Dynamic Approach－
  2. 2-2 Understanding Containment Vessel Flow During Severe Accident
    －Mass Transport Behavior Depending on the Relative Location of Outer Cooling and Initial Stratification－
  3. 2-3 Fuel Debris Form Prediction in a Severe Accident
    －Measurements of Mass Fractions of Agglomerated Debris Settled on the Floor of a PCV－
  4. 2-4 Parameter Determination for Assessing the Sheltering Effectiveness in Japanese Houses
    －Obtaining Data on Penetration Factor and Deposition Rate of Particulate and Elementary Iodine by Real House and Chamber Experiment－
  5. 2-5 How Much Can Nuclear Piping Withstand Huge Earthquakes
    －Development of Seismic Fragility Evaluation Method for Aged Piping－
  6. 2-6 A Path Toward Recycling and Landfill of Asbestos Waste Arising from Decommissioning
    －Development of Evaluation Method for Exposure Dose by Cleared Asbestos Waste－
  1. 3-1 What is the Chemical Behavior of the Heaviest Element?
    －A Small Breach of the Periodic Law Found in the Volatility of Element 105, Dubnium－
  2. 3-2 Probing the Strong Interaction with Superconducting Detectors
    －Drastic Precision Improvement in the X-Ray Spectroscopy of Kaonic Atoms－
  3. 3-3 Slow Dynamics of Electrons in Uranium Compounds
    －Approaching the Mystery of Superconductors Leading to Quantum Computers－
  4. 3-4 Topology-Based Manipulation of Magnets in Spintronics
    －New Principle for Power Saving in Magnetic Memories－
  5. 3-5 Insight into Designing Highly Efficient Ortho-Para Hydrogen Conversion Catalysts
    －Demonstration of Fast Ortho-Para Conversion of H2 on a Stepped Surface－
  6. 3-6 Unveiling the Retention Mechanisms of Uranium (VI) on Host Rocks
    －Surface Sorption Process Related to Two Types of Sorption Species－
  7. 3-7 Towards Understanding the Coherent Properties of Bosons
    －Determination of the Josephson Current in a Bose-Einstein Condensate－
  1. 4-1 Development of a Low-Cost Transportable Device for Detecting Nuclear Materials
    －Successful Experimental Demonstration of a New Nondestructive Method－
  2. 4-2 Connecting Nuclear Data with Transport Calculation
    －Development of Nuclear Data Processing Code FRENDY Version 2－
  3. 4-3 Unveiling the Mystery of the Radiation Damage that Does Not Follow the Conventional Theory
    －Radiation Damage Mechanism in Ceramics Irradiated with Swift Heavy Ions－
  4. 4-4 Detailed Radioactive Plume Dispersion and Dose Calculations Considering Buildings in Local Areas
    －Development of a Local-Scale High-Resolution Atmospheric Dispersion and Dose Assessment System－
  5. 4-5 Nuclear Fuel Cycle Simulator NMB4.0 Released
    －Development of Fast, Versatile, and Flexible NMB4.0 to Contribute to the Planning of Future Nuclear Energy Utilization Strategies－
  6. 4-6 Toward the Realization of a Reliability-Oriented Accelerator for the Accelerator-Driven System
    －Robust Beam Optics Design of a 30-MW LINAC for Nuclear Transmutation－
  7. 4-7 Improving Adsorption Capacity for Medical Radioisotopes
    －Elucidation of Molybdate Ion Adsorption Mechanism in Alumina－
  1. 5-1 Beam Measurement Using Light Produced by Beam-Gas Interaction
    －Development of a Gas Sheet Beam Profile Monitor－
  2. 5-2 Acceleration of Neutron Measurement by Deep Learning
    －Over 10-Fold Acceleration of Neutron Reflectometry Measurement by an Accurate Noise Reduction Method－
  3. 5-3 Wide Bandwidth Neutron-Spin Polarizer
    －A Breakthrough in Neutron-Polarizing Supermirror with Very High Critical Momentum Transfer－
  4. 5-4 Discovery of Coupled Fluctuations with Protein Domain Structures and Active Sites
    －Analysis of Protein Dynamics by Neutron Scattering and Molecular Simulation－
  5. 5-5 Development of Nuclear Vitrification by Neutron Scattering
    －Nanoscopic Structure of Borosilicate Glass with Additives－
  6. 5-6 Fabrication of Environment-Friendly Piezoelectric Materials
    －Local Structural Analysis of Bi0.5Na0.5TiO3 in the High-Temperature Phase－
  7. 5-7 How Heavy Electrons are Formed in Eu-Based Compounds
    －Direct Observation of the Band Structure of Eu 4f Orbitals, Which Have Magnetic and Localized Characteristics, by Synchrotron Radiation Experiments－
  1. 6-1 New Seismic Classification of the HTTR
    －Appropriate Seismic Classification Based on Technical Knowledge and Operation Experience－
  2. 6-2 Challenge to Measure the Power Distribution in Very-High-Temperature Core Environments
    －Development of a Power Distribution Measurement Method Using Neutrons Leaked from an HTGR Core－
  3. 6-3 For Reducing the Cost of Construction of High-Temperature Gas-Cooled Reactors
    －Development of Cesium Trap Material for Coated Fuel Particles－
  4. 6-4 Upgrading H2 Production Efficiency in the IS Process
    －Corrosion Stability Improvement of the H2 Separation Membrane for HI Decomposition－
  5. 6-5 Achievement of Longer-Term H2 Production in IS Process
    －Introduction of a Novel Operating Procedure Using a Closed-Loop System－
  6. 6-6 Development of a Novel RPV Cooling System for HTGRs
    －Comparison of the Structural Differences Between RPV Cooling Systems and Effects of External Parameters on RPV Cooling－
  7. 6-7 Toward More Accurate Core Analysis of High-Temperature Gas-Cooled Reactors
    －Development of a Core Analysis Method with Specified Graphite Porosities－
  1. 7-1 Fast Simulation Method for Chemically Reacting Flows
    －Efficient Numerical Simulation for Developing New-Generation Nuclear Plants－
  2. 7-2 Understanding Aerosol Behavior in Fast Reactor Accidents
    －Test on Aerosol Transport Behavior Using the MET Facility－
  3. 7-3 Failure Prediction of Fast Reactor Components
    －Cyclic Loading Test and Failure Prediction of Multiperforated Plates－
  4. 7-4 Capturing the Oxygen Diffusion Phenomena in Nuclear Fuel
    －Measurement and Evaluation of the Oxygen Self-Diffusion Coefficient of MOX Fuel－
  5. 7-5 Development of Fast Reactor Fuel for Reduction of Radioactive Waste
    －Evaluation of Thermal Conductivity of High Am-Bearing Mixed Oxide Fuel on Stoichiometry－
  6. 7-6 Evaluation of Experiments in the Prototype Fast Reactor Monju
    －Solving Discrepancy Between Measurement and Calculation－
  7. 7-7 Toward Realization of Advanced MOX Fuels
    －Measurement of Slight Variations in the Oxygen Content of Fuels－
  1. 8-1 Toward the Design of the Disposal Facilities Considering the Environmental Standards
    －Change in Uranium Concentration in Groundwater Depending on the Facility Layout and Structure－
  2. 8-2 Establishment of a Treatment Method for Nuclear Fuel Material for Safe Storage
    －Stabilization Treatment of Nuclear Fuel Material Containing Organic Compounds－
  3. 8-3 Toward Stabilization of Hazardous and Radio-Active Wastes
    －Characterization of Lead Stabilized with Alkali-Activated Material－
  4. 8-4 Coating Removal Technique for Painted Steel Surface
    －Performance Evaluation of Laser Cleaning－
  5. 8-5 Decommissioning of a Facility with a History of Contamination Caused by a Fire Disaster in a Controlled Area
    －Collective Dismantling of the Uranium Enrichment Laboratory Using a Large Isolation Tent－
  6. 8-6 Dismantling a Tank Containing Liquid with α Nuclides
    －Exposure Reduction Measures and Acquisition of Work Data for Future－
  7. 8-7 New Method to Observe Fault Displacement Using a Conventional Device
    －Significant Progress Toward Greatly Enhanced Underground Utilization－
  8. 8-8 Prediction of the Low-Permeability Domain in Soft Rock
    －Estimation of the Effective Hydraulic Conductivity by Hydromechanical Simulation－
  9. 8-9 Discriminating Tephra with Similar Chemical Compositions
    －Development of a Method for the in Situ Chemical Composition Analysis of Volcanic Glasses－
  10. 8-10 Prediction of Radionuclide Migration by a Thermodynamic Sorption Model
    －Assessing the Impact of the Transition of Repository Condition on Radionuclide Migration－
  11. 8-11 Migration Behavior of Carbon-14 in Buffer Material
    －Diffusion Experiments of Carboxylic Acid and Alcohol in Compacted Bentonite－
  1. 9-1 Deep-Learning Model for High-Resolution Steady Flow Prediction
    －Convolutional Neural Networks for Multiresolution Steady Flow Prediction－
  2. 9-2 Acceleration of Multiscale Fluid Simulation on GPU Supercomputer
    －Communication Reducing Method for Local Mesh Refinement－
  3. 9-3 Detecting the Quantum Fluctuation of Water
    －High-Precision Calculations of Water Using the General-Purpose Molecular Simulation Code PIMD－
  4. 9-4 Clarification of the Fundamental Properties of Radium
    －Ab Initio Molecular Dynamics Simulations and Extended X-Ray Absorption Fine Structure Measurements Revealed the Hydration Structure of Barium－
  1. 10-1 Development of a Compact Nondestructive Analysis System for Measuring Nuclear Material
    －Demonstration of Neutron Resonance Transmission Analysis System Using a Laser-Driven Neutron Source－
  1. 1-1 Revealing the Characteristics of Fuel Debris
    -Formation Mechanisms of Metallic Fuel Debris Originating from Control Rods-
  2. 1-2 Development of Radiation Detector for Non-Destructive Assay of Nuclear Fuel Debris
    -γ-ray Spectrometry System Specific to High Dose-Rate Measurements Using CeBr3-
  3. 1-3 Chemical Forms of Radionuclides in Fuel Debris
    -Structure of Concrete Interaction Products and Distribution of Sr and Ba-
  4. 1-4 To Establish Safer Criticality Management of Fuel Debris
    -Optimization of the Core Configuration of the New STACY for Debris Simulation-
  5. 1-5 Methodology to Remove Cs from Soil
    -Preparation for the Treatment of Contaminated Soil-
  6. 1-6 Toward Understanding Core Melting Behavior in RPVs
    -Evaluation of RPV Failure Mechanism-
  7. 1-7 Laser Ultrasonic Approach to Detect Corrosion of Reinforced Concrete
    -Toward Nondestructive Testing Technology for Decommissioning-
  8. 1-8 Aiming to Predict PCV Corrosion
    -Development of Corrosion Database under Varying Irradiation Conditions-
  9. 1-9 Radiation Position Detection under High Dose Rate Using Optical Fibers
    -An Approach to Detect the Position of Radiation Focusing on the Wavelength Information of Light-
  10. 1-10 Impact of Large Typhoons on the Estuary Mass Flux
    -Observation of Radioactive Cesium in the Estuary in 2019-
  11. 1-11 Visualization of Radiological Map Using Machine Learning
    -Analytical Method Using Big Data of Radiation Measurements in Fukushima-
  12. 1-12 Improving the Accuracy in Estimation of Air Dose Rate Decrease
    -A New Model for Simulation of Temporal Changes Due to an Environmental Effect-
  13. 1-13 Sediment Characteristics Determine the Behavior of Cesium in Rivers
    -Adsorption/Desorption Mechanism of Radioactive Cesium onto River Sediments-
  14. 1-14 Remobilization of Radiocesium from Sediments
    -Mass Balance of Dissolved 137Cs in an Artificial Reservoir in Fukushima-
  15. 1-15 Rapid Analysis of 90Sr in Small Bone Samples
    -Applicability of Sr Resin for ICP-MS of 90Sr in Hard Tissues-
  16. 1-16 Speciation of Cs in Tree Tissues
    -Elucidation of the Mobility of Cs inside Trees Using Synchrotron Radiation-
  17. 1-17 Where Does the Radiation Determining Air Dose Rates in Forests Originate?
    -Simulations Reveal the Connection between the Movement of Radioactive Cesium and Air Dose Rate Trends-
  18. 1-18 Understanding the Cesium Adsorption Behavior in Concrete
    -Accurate Simulation of Cement Hydrate Using Machine Learning Molecular Dynamics-
  1. 2-1 Reliable Thyroid Dose Measurement after a Severe Nuclear Accident
    -Developing a Portable Thyroid Dose Monitor-
  2. 2-2 Can Contaminated Monitoring Posts Measure Accurately in a Nuclear Accident?
    -Influence of Contamination on Measured Dose Rates at Monitoring Posts-
  3. 2-3 Prediction of Structural Damage from Projectile Impacts
    -Numerical Evaluation of Penetration Damage under Realistic Conditions-
  4. 2-4 Accident Simulation: HLLW Evaporation to Dryness
    -Evaluating the Restraint Effect on the Release of Volatile Ruthenium-
  5. 2-5 A Nonparametric Bayesian Method for Predicting the Embrittlement of Reactor Pressure Vessels
    -Toward Further Reliability of Integrity Assessment in Long-Term Operation-
  6. 2-6 Migration of Radionuclides from Radioactive Wastes of Reactor Core Structures in Underground Environments
    -Modeling Niobium Sorption onto Clay Minerals in the Presence of Calcium-
  7. 2-7 Detection of Undeclared Uranium Purification Activities
    -230Th/234U Radio-Chronometry with a Single Uranium Particle-
  8. 2-8 Operating Robots Entering the Accident Site on Behalf of a Person
    -Training of Robot Operators for Nuclear Disaster Response-
  1. 3-1 Nuclear Fission Unveiled via Multinucleon Transfer Reaction
    -Opening Fission Research in Unexplored Region of the Chart of Nuclei-
  2. 3-2 Determination of the Mass of a Ξ Hypernucleus
    -New Information to Understand the Structure of Neutron Stars-
  3. 3-3 Magnetic Cooling to Near Absolute Zero Temperatures
    -Cooling to Extremely Low Temperature Realized by Quantum Fluctuations in "Ytterbium Magnet"-
  4. 3-4 For a Radio-Resistant Thermoelectric Generation System
    -Tolerance of Spin Thermoelectric Devices for Radiation-
  5. 3-5 Elucidation of Low-Energy Vibrational Modes of Deuterated Water Clusters
    -Utilization of Terahertz-Infrared Absorption Spectroscopy and Ab Initio Calculation-
  6. 3-6 Exploration of the Exotic Structure of Pc
    -Hybrid State with a Mixture of Compact State and Hadron Molecule-
  1. 4-1 Toward High-Energy Neutron Applications
    -Development of Nuclear Reaction Database for Basic Sciences and Medicine-
  2. 4-2 Estimating Nuclear Data Using a Machine Learning Technique
    -Toward the Development of a High-Quality Nuclear Reaction Database-
  3. 4-3 Toward Clarifying the Chemical States of Nuclear Fuel Debris
    -Applicability of Micro-Raman Spectroscopy-
  4. 4-4 Reassessment of Atomic Bomb Survivor Doses
    -Joint Japan-U.S. Study to Improve Epidemiological Research Accuracy-
  5. 4-5 Quicker Calculation of Atmospheric Dispersion of Radioactive Materials under Various Conditions
    -Development of the Atmospheric Dispersion Database System WSPEEDI-DB-
  6. 4-6 Clarification of the Spontaneous Microcracking of Aluminum Alloys
    -Toward the Realization of High-Strength Alloys through Computational Science-
  7. 4-7 Extent of Damage to Material when Exposed to Proton Beam
    -Contribution to the Safety of Accelerator-Driven Systems-
  1. 5-1 Toward Stable Operation of a High-Intensity Proton Beam
    -Development of an Online Monitoring System for the Injection Stripper Foil-
  2. 5-2 Strengthening Mechanism of Cast Iron Elucidated by a High-Intensity Pulsed Neutron Beam
    -Deformation Response of Each Constituent Phase Monitored by Neutron Diffraction-
  3. 5-3 Realization of a Highly Polarized Neutron Beam across a Wide Energy Range
    -Development and Application of a Neutron Polarization Device Using Highly Polarized 3He-
  4. 5-4 Strange Short-Range Order of Conduction Electron Spins Realized at High Temperatures
    -Unexpected State Found in the Newly Synthesized Magnet, Mn3RhSi-
  5. 5-5 Development of a Metal Adsorbent Using Bone Waste
    -A Low-Cost and High-Performance Metal Adsorbent Prepared from Food Waste-
  6. 5-6 Fast Molecules Passing through Carbon-Atom Net
    -Discovery of Oxygen Molecules Slipping through Graphene-
  7. 5-7 Atomic-Level Observation of Magnetic Ordering Process in Ferromagnetic Semiconductors
    -Exploring the Mechanism of Ferromagnetism for Its Practical Use in Spintronics Devices-
  1. 6-1 Prediction of Thermal-Hydraulic Behavior in HTGR Accidents
    -Development of Evaluation Methodology of Air-Ingress Behavior in HTGR-
  2. 6-2 Nuclear Design Policy to Maintain the Integrity of Coated Fuel Particles
    -Derivation of the Ideal Power Distribution to Minimize the Kernel Migration Rate-
  3. 6-3 Toward the Realization of High Temperature Gas-Cooled Reactor for Safe Reduction of Plutonium Inventory
    -Microstructure Observation of a Simulated Fuel Kernel-
  4. 6-4 Toward Metallic Sulfuric Acid Decomposers in the IS Process
    -Discovery of Steel Materials with Corrosion Resistance Equivalent to Ceramics in a Sulfated Gas Environment-
  5. 6-5 Membrane Technique Advancing the IS Process
    -Enhancement of the HI Conversion by Silica-Based Membrane Reactor-
  6. 6-6 Energy Saving of the Main Reaction in the IS Process
    -Membrane and Electrode Development for the Bunsen Reaction Overvoltage Reduction-
  7. 6-7 Shortening the Calculation Working Time for the Criticality Control Rod Position
    -Development of a Utility Tool for Auto Seeking the Critical Control Rod Position-
  1. 7-1 Observation of Nuclides Adsorbed inside the Column Using Neutrons
    -Non-Destructive Visualization of Nuclides by Resonance Neutron Imaging-
  2. 7-2 Improvement of the Calculation Accuracy of Power Distribution for Large Fast Reactors
    -Refinement of Control-Rod Calculation Method-
  3. 7-3 Clarification of the Relocation Behavior of Degraded Fast Reactor Core Materials under Severe Accident
    -Development of Thermophysical Properties Database for Stainless Steel Containing Boron Carbide-
  4. 7-4 Optimization of Alloying Components of Nuclear Core Materials
    -Development of an Estimation Method for Irradiation-Induced Point Defect Behavior-
  5. 7-5 Improvement and Demonstration of an Extraction Chromatography Flow-Sheet to Recover Trivalent Minor Actinides
    -Efficient MA(Ⅲ)/Ln(Ⅲ) Separation Process-
  1. 8-1 Implementation of Disposal Project of LLW Generated in Research, Medical, and Industrial Facilities
    -Preparation of “Concentration Equivalent Dose Criteria” as the Standard for the Selection of Important Nuclides-
  2. 8-2 Recovery of Nuclear Materials from Spent Extraction Solvent Using Solid Adsorbent
    -Investigation of Complex Formation Reaction of Iminodiacetic Acid Group in Solvent-
  3. 8-3 Turning Difficult-to-Treat Wastes into Stable Waste Packages
    -Investigation of Radioactive Aluminum Waste Treatment Technology Using the Bayer Process-
  4. 8-4 Safety Improvements for Plutonium-Handling Facilities
    -Development of Fireproof Sheet on Glove Box Panels-
  5. 8-5 Direct Observation of the Fracture Induced by Gallery Excavation
    -Visualization Technology Using a Resin Injection Method-
  6. 8-6 Factors Affecting Rock Desaturation in Tunnel Excavation
    -Numerical Simulation on the Effects of Dissolved Gas and Rock Permeability-
  7. 8-7 From Micro to Macro: Approaching Mountain Formation Processes Based on Age Determinations of Minerals
    -Insights to the Ou Backbone Range Obtained from Low-Temperature Thermochronology-
  8. 8-8 Reduced Geological Sample Size for Radiocarbon Dating at JAEA-AMS-TONO
    -Preparation Techniques Using One-Twentieth the Sample Size of the Conventional Method-
  9. 8-9 Safety Assessment Considering the Evolution of Topography and the Depth of the Disposal Facility
    -Development of an Analysis Tool to Evaluate the Topography and Depth of a Disposal Facility-
  10. 8-10 Electrochemical Methods to Evaluate Overpack Corrosion
    -Search for Passivation Conditions of Carbon Steel Surrounded by Buffer Material-
  1. 9-1 Plume Dispersion Simulations Satisfying Accuracy Criteria for Environmental Assessments
    -Real-Time Ensemble Calculations with Meter-Order Resolution-
  2. 9-2 Exascale CFD Simulations on Fugaku and Summit
    -Development of Mixed-Precision Matrix Solvers for Many-Core CPUs and GPUs-
  3. 9-3 Theoretical Prediction of “Fermi Arc”
    -Development of Novel Method for Analyzing Strongly Correlated Electrons in Heavy-Element Compounds-
  4. 9-4 Prevention of Hydrogen Embrittlement in Aluminum Alloys
    -Identification of the Intermetallic Compounds that Take Away Hydrogen from Aluminum Lattice-
  1. 10-1 Toward a World without Nuclear Weapons and Nuclear Terrorism
    -Case Study and Factor Analysis of Denuclearization-
  1. 1-1 Evaluation of Uranium Leaching from Fuel Debris in Water
    －Leaching Rate Evaluation Considering Effects of Concrete Components, and Comparison with Spent Fuel－
  2. 1-2 Distribution of Components in Fuel Debris
    －Segregation of Gadolinium and Iron during Solidification Using Simulated Molten Debris－
  3. 1-3 50x Increase in Plasma Emission Intensity by Microwave
    －Advanced Remote Analysis Technology for Fuel Debris Using Laser-Induced Breakdown Spectroscopy－
  4. 1-4 Clarifying the Warming Behavior of a Robot Test Pool
    －Measurement and Analysis toward Facility Utilization with User Needs－
  5. 1-5 3D Reconstruction of Structures from Images
    －Development of Image Analysis Method to Support Remote Operation－
  6. 1-6 Chemisorption of Cesium on Structural Materials during SA
    －Prediction and Verification of Thermodynamic Properties of Cesium Compounds－
  7. 1-7 Hydrogen Release from Geopolymer by Gamma Irradiation
    －Reduced Hydrogen Yield of Bulky, Solidified, Water-Saturated Waste－
  8. 1-8 Accident Progression Analysis: Units 1−3 at the Fukushima Daiichi NPS
    －Insights from International Benchmark Analysis Project－
  9. 1-9 Cause of Cesium Concentration Change in Fish
    －Three Transport Pathways from Forests to Fish－
  10. 1-10 Fast and Easy Analysis of Tritium in Plants and Animals
    －Development of Rapid Organically Bound Tritium (OBT) Analysis in Marine Products－
  11. 1-11 How Does the Dose Rate Change after Decontamination?
    －Effects of Land Use Type Revealed from Long-Term Monitoring Data－
  12. 1-12 Radiocesium Behavior in River System
    －Relationship between Mineral Species and Radiocesium in Riverbed Using Microscopy－
  13. 1-13 Cause of Radioactivity Concentration in Mushrooms
    －Cesium Selectivity Evaluation of Mushroom Pigment Norbadione A－
  14. 1-14 Estimation of Total Radiocesium Discharged from Fukushima Daiichi NPS to the Coast
    －Discharge Inventory Decreased to Approximately 1/100000th Since the Accident－
  15. 1-15 Reconstruction of Atmospheric Release and Dispersion of Radioactive Materials by Computer Simulation
    －Contribution to the Refinement of Dose Assessment in the Early Stage of the Accident by Improving the Dispersion Calculation Optimization Method－
  16. 1-16 Initial Air Dose Rate after the Accident at the Fukushima Daiichi NPS
    －Comparison between Fukushima and Chernobyl－
  17. 1-17 Analyzing Decreasing Trends in Radioactivity and Dose Rate
    －Changes of Radiocesium Concentration in Soil and Air Dose Rate over Five Years－
  18. 1-18 Assessment of External Exposure Doses in Daily Life
    －Development of Assessment Model Based on Local Radiation Surveys－
  1. 2-1 Measurement of Very Thin Liquid Film Thickness
    －Technical Development for the Evaluation of Liquid Film Dryout Behavior－
  2. 2-2 Reliable Safety Evaluation for Reactivity-Initiated Accidents
    －Mechanical Property Evaluation of Fuel Cladding under Biaxial Stress Conditions－
  3. 2-3 Effects of Stress on Oxidation near a Crack Tip
    －Toward an Understanding of the Mechanism of Environmentally-Assisted Cracking in Stainless Steel－
  4. 2-4 Preparing for Aftershocks after a Major Earthquake
    －Proposal of Risk Assessment Method Considering Large Aftershocks－
  5. 2-5 Elucidating HEPA Filter Clogging under Organic Solvent Fire
    －Development of Severe Accident Assessment Method for Reprocessing Facilities－
  6. 2-6 Rapidly and Widely Measuring Radiation from the Sky
    －Preparedness for Using Aerial Radiation Monitoring during a Nuclear Emergency－
  1. 3-1 Observing Giant Dipole Vibration in Fission Fragments
    －Toward Understanding the Fission Process－
  2. 3-2 Improving the Extraction Efficiency by Preventing Aggregation Phenomena of a Complex
    －Development of a Solvent Extraction Method Using the Strong Hydrophobicity of Fluorine－
  3. 3-3 Clarifying the Mechanism behind Superconductivity in Uranium Compounds
    －NMR Research to Reveal the Mechanism of Spin-Triplet Superconductivity－
  4. 3-4 Detection of the Singularity of Magnets Using Rotation
    －Measuring the Angular Momentum Compensation, Key to Speeding Up Magnetic Devices－
  5. 3-5 Closing in on the Longstanding Puzzle of Localized Electrons in an Electron-Conducting Oxide
    －Using Muons to Unveil the Nature of Localized Electrons in Hydrogen-Doped SrTiO3－
  6. 3-6 Revealing Unique Nucleus Shapes by Nuclear Reactions
    －Cluster Structure and Its Probability－
  1. 4-1 Development of Photonuclear Data Library for International Contribution
    －Accomplishment of a Reliable Database Supporting the Use of Photonuclear Reactions－
  2. 4-2 Development of Nuclear Data for LLFP Transmutation
    －Models to Predict the Nuclear Cross-Section of Long-Lived Fission Products (LLFPs)－
  3. 4-3 Accelerated Corrosion of Low-Alloy Steel at the Air/Solution Interface
    －Clarification of Corrosion Acceleration Mechanism from Structural Analysis of Rust Layer－
  4. 4-4 Extension of Applicable Range of ESR Dosimetry via Enamel Separation Techniques
    －External Exposure Dose Estimation of Wild Japanese Macaque in Fukushima Prefecture－
  5. 4-5 Real-Time Estimation of Radiation Dose at Flight Altitudes
    －Development of Warning System for Aviation Exposure to Solar Energetic Particles (SEPs)－
  6. 4-6 Separation of Minor Actinides Using Incinerable Extractants
    －Recovery of Minor Actinides and Rare Earth Elements in a Concrete Cell－
  7. 4-7 Validation of Nuclear Design Accuracy for ADS
    －Critical Experiment with Plutonium Fuel－
  8. 4-8 Development of Beam Window Materials for ADSs
    －Post-Irradiation Examination of Beam Window Materials through International Project－
  1. 5-1 Toward Upgrading High-Intensity Proton Accelerators
    －A Radio Frequency Quadrupole Linac Using a New Beam Dynamics Design Scheme－
  2. 5-2 Detection of Change in Hydrogen Bond in the Deep Earth
    －Direct Observation of Symmetrization at High Pressure by Neutron Diffraction－
  3. 5-3 Mitigation of Damage to the Target Vessel Wall
    －Enabled High-Power Spallation Neutron Target by Double-Walled Structure－
  4. 5-4 Enabling Material Analysis with Neutron Beams at Manufacturing Sites
    －Texture Measurement of Steel Materials Using a Compact Neutron Source－
  5. 5-5 Elucidation of Structural Fluctuations of Proteins
    －Observation of Structure and Dynamics of Protein by Neutron Scattering－
  6. 5-6 Structural Analysis of Ionic Liquid−Electrode Interface
    －Nano-Scale Analysis of the Interfacial Structure Using a Quantum Beam－
  7. 5-7 Toward Next-Generation Memory with Low Power Consumption
    －Observation of Electronic Structure of Alumina Film for Nonvolatile Memory－
  8. 5-8 Observation of Electrons in Unconventional Uranium Superconductor
    －First Observation of the Electronic Structure of UTe2－
  1. 6-1 Whole Core Burnup Characteristic Evaluation Method Using Representative Impurities
    －Cost Reduction for HTGRs Using Inexpensive Graphite Materials－
  2. 6-2 A Threefold Increase in Burnup of HTGR Fuel
    －Development on High-Burnup HTGR Fuel under International Cooperation－
  3. 6-3 Toward Harmonization with Renewable Energy
    －HTGR Concept for Accomplishing Hybrid Operation with Renewable Energy－
  4. 6-4 Toward Commercial Implementation of the IS Process with HTGRs for Hydrogen Production
    －Development of Strength Evaluation Method for Ceramic Structures－
  5. 6-5 Toward Metallic Sulfuric Acid Decomposers in the IS Process
    －Development of a Corrosion Test Apparatus without Sulfur Dioxide (SO2) Leakage－
  6. 6-6 Toward Stable and Continuous Hydrogen Production by the IS Process
    －Development of a Pump Shaft Seal Technology for HI Solution Including Highly Concentrated I2－
  7. 6-7 Impact of Exhaust Stack Collapse on the Reactor Building
    －Confirmation of the Integrity of the Reactor Building by 3D Model Collision Analysis－
  1. 7-1 Toward Efficient Manufacturing of the Above-Core Structure
    －Routing Study of the Above-Core Structure with a Mock-Up Experiment－
  2. 7-2 Reliable Decay Heat Removal by Natural Convection
    －Core Cooling Experiment Using Dipped DHX and Development of Evaluation Method－
  3. 7-3 Development of Fuel Assembly Analysis Method in Fast Reactors
    －Prediction of Thermal Hydraulics in Fuel Assembly with Inner Duct Structure (FAIDUS)－
  4. 7-4 Development of Ultra-High Temperature Tolerant Fuel Claddings
    －Mechanical Properties of Oxide Dispersion Strengthened Steel Claddings at 1000 °C－
  5. 7-5 Exploring an Ignition Mechanism of Hydrogen with Burning Sodium Mist
    －Visualizing the Ignition Process of Hydrogen Jets Containing Mist Caused by Sodium Leaks in Severe Accidents－
  1. 8-1 Toward Public Use of the Decommissioning Cost Estimation Code DECOST
    －Development of a Manual for the DECOST－
  2. 8-2 Radioactive Waste Confirmation Method for Rational Disposal
    －Study on the Evaluation Methodology of Wastes Generated from Post-Irradiation Examination Facilities－
  3. 8-3 Complex Biological Effect of Low-Dose Radiation
    －Feature Extraction of Multidimensional Data Using Machine Learning－
  4. 8-4 Radioactive Liquid Waste Management Technologies
    －STRAD Project for the Treatment of Radioactive Liquid Waste-Containing Chemicals－
  5. 8-5 Assessing Underground Fracture Connectivity from the Surface
    －Development of a Single Borehole Investigation Method－
  6. 8-6 Change in Permeability after Backfilling a Research Tunnel
    －Change in Hydraulic Conductivity in the Simulated Realistic Disposal Environment－
  7. 8-7 Chemical Signatures Suggesting Recent Fault Activity
    －Detection of Elemental Changes due to Fault Activity－
  8. 8-8 Visualization of Long-Term Variability in Groundwater Flow Conditions
    －Development of Evaluation Method for Variability of Groundwater Flow Conditions－
  9. 8-9 Mechanical Modeling of Buffer Materials
    －Applicability of Elasto-Plastic Constitutive Model under Saltwater Conditions－
  10. 8-10 Unveiling the Interaction Mechanism of Fe (II) and Si
    －Characterization of Ferrous Silicate Co-Precipitates under Reducing Conditions－
  11. 8-11 Analysis of Radioactive Samples by Plasma Generated in the Microchannel
    －Determination of Cesium in Highly Radioactive Liquid Waste by Liquid Electrode Plasma Optical Emission Spectrometry－
  1. 9-1 CFD Simulation of a Fuel Debris Air-Cooling Experiment
    －Validation of a Thermal-Hydraulic Model Using the Lattice Boltzmann Method－
  2. 9-2 Using Computer Simulations to Design a Superconducting Neutron Microscope
    －Simulating All Radiation Types inside the Neutron Microscope and Predicting Its Behavior－
  3. 9-3 Understanding the Deformation of Iron from the Movement of Atoms
    －Analysis of Screw-Dislocation Motion and Slip-Plane Transition by Atomistic Simulations－
  4. 9-4 Multi-Phase Fluid Simulations Using the World?fs Largest GPU Supercomputer
    －Development of Communication-Avoiding Matrix Solvers on GPU－
  1. 10-1 Nondestructive Assay of Nuclear Materials for Safeguards
    －Developing Practical Delayed Gamma-ray Spectroscopy Using PUNITA－
  1. 1-1 Estimate the State of the RPV and PCV after a Severe Accident
    －Upgrading of the Comprehensive Identification of Conditions Inside Reactor－
  2. 1-2 Numerical Evaluation of Fuel Debris Hardness
    －First-Principle Calculation of the Mechanical Properties of Fuel Debris－
  3. 1-3 Degradation Mechanism of a BWR Control Blade
    －Understanding the Behavior of Boron Compounds during a Severe Accident－
  4. 1-4 Uncertainty Estimation in the Criticality of Nuclear Systems Containing Fuel Debris
    －Development of a Criticality Calculation Method for Randomly Distributed Materials－
  5. 1-5 Measuring Alpha-Particle Emitters Flying in Nuclear Facility Buildings
    －A Highly Reliable Alpha Dust Monitor Using a GPS Scintillator Plate－
  6. 1-6 Determination of the Optimum Shape of Hydrogen Recombination Catalysts
    －Hydrogen Elimination Effect Experimentally Verified for Full-Size Equipment－
  7. 1-7 Estimating Radioactive Waste Inventory
    －Sorption Behavior of Actinides on Zeolite－
  8. 1-8 Towards Routine Analysis of Difficult-to-Measure Radionuclides
    －Preparation of Analysis Manuals for 93Zr, 93Mo, 107Pd, and 126Sn Waste－
  9. 1-9 Assessing the Safety of Reusing Contaminated Rubble
    －Restricted Reuse in the TEPCO’s Fukushima Daiichi NPS Site－
  10. 1-10 Development of Robot Simulator for Decommissioning Task Training
    －Multi-Copter Simulator and Virtual Operator Proficiency Training System－
  11. 1-11 Observed Decrease of Radiocesium in River Water
    －Result of Three-Year-Long Observation－
  12. 1-12 Radiocesium Behavior from Forest to Stream Water and River
    －Understanding How Dissolved Radiocesium is Discharged from Upstream－
  13. 1-13 Clarifying the Distribution of Sediment-Associated Radiocesium at the Bottom of a Pond without Sediment Sampling
    －Visualizing the Vertical Distribution of Sediment-Associated Radiocesium－
  14. 1-14 Exploring the Migration of Radionuclides to the Deep Ocean
    －Elucidation of Subduction from the Vertical Distribution of Concentration－
  15. 1-15 Quickly and Accurately Measuring Environmental Radiation Levels
    －Advanced Conversion Method for Airborne Radiation Monitoring－
  16. 1-16 Evaluating the Effective Dose Based on a Detailed Radiation Map
    －Providing Protection from Radiation in the Specified Reconstruction and Revitalization Base－
  17. 1-17 Modeling the Distribution of Air Dose Rates in Habited Areas of Fukushima Prefecture
    －Developing the 3D Air Dose Rate Evaluation System－
  1. 2-1 Uncertainty Reduction in Source Term Evaluation
    －Dependence of Decontamination Factor on Aerosol Particle Number Concentration in Pool Scrubbing－
  2. 2-2 Toward a More Reliable Safety Evaluation for Loss-of-Coolant Accidents
    －Uncertainty Quantification of Fracture Limit of Fuel Cladding Tube－
  3. 2-3 Safety Evaluation Considering Uncertainties of Accident Progression
    －Development of Simulation-Based Risk Assessment Methodologies－
  4. 2-4 Evaluating of Sheltering Effectiveness against Internal Exposure at a Nuclear Accident
    －Factors Affecting Sheltering Effectiveness and Influence of Environmental Factors on Indoor/Outdoor Ratio－
  5. 2-5 Detailed Investigation of the Fracture Toughness of a Reactor Pressure Vessel
    －Fracture Toughness Evaluation of Heat-Affected Zone under Overlay Cladding Using Miniature Specimen－
  6. 2-6 More Rational Inspection of the Piping System
    －Evaluating the Ratio of Welds to be Inspected Based on a Risk Informed In-Service Inspection－
  1. 3-1 Unveiling the Unique Fission Process of Fermium Nuclides
    －Clues towards Understanding the Existing Limit of Super-Heavy Elements－
  2. 3-2 How Removal of Strontium from Seawater ?
    －Use of Coprecipitation Method by Barite Controlled Chemical Composition－
  3. 3-3 Observation of a New Double Lambda Hypernucleus during a J-PARC Experiment
    －As a Microscopic Image, the Second Case Where the Nuclide is Identified－
  4. 3-4 Superconductivity Driven by Ferromagnetic Fluctuations in the Uranium Compound UGe2
    －Correlation between Superconductivity and Ferromagnetic Fluctuations Studied by Magnetic Measurements at High Pressure－
  1. 4-1 Contribution by Nuclear Physics to Transmutation Study
    －Accurate Prediction of Deuteron Transmutation－
  2. 4-2 Microscopic Corrosion Behavior in High-Temperature, High-Pressure Environments
    －In-Situ Measurement of Electrical Conductivity of Solution in Stainless Steel Crevices－
  3. 4-3 Origin of Am/Cm Selectivity Elucidated by Chemical Bonding
    －Focusing on the Covalent Interaction between Metal Ions and Separation Ligands－
  4. 4-4 Accurate Detection of Particles in Accelerators, Space, and Medicine
    －Understanding the Mechanism that Determines the Scintillation Light Yields－
  5. 4-5 Evaluation of Exposure Doses Considering Variations in Physiques of Japanese
    －Completion of Adult Japanese Human Model Series－
  6. 4-6 Estimation of Fission Product in a Light Water Reactor under a Severe Accident
    －Development of Fission Product Chemistry Database ECUME－
  7. 4-7 Improving the Prediction Accuracy of Spallation Product Yields
    －Improving a Stochastic Model of Nuclear Fission Induced by a High-Energy Particle－
  1. 5-1 Long-Term, Stable Production of a High-Intensity and High-Quality Beam
    －Development of an RF-Driven Negative Hydrogen Ion Source－
  2. 5-2 Linking Spin-Fluctuations to Electron Correlations
    －A Combined Neutron and ARPES Study－
  3. 5-3 Two-Dimensional Neutron Measurement with High Sensitivity and High Precision
    －Development of a Bump Cathode Neutron Detection Element－
  4. 5-4 Measuring the Neutron Brightness Distribution from Liquid Hydrogen Moderators
    －Measuring and Validating the Neutron Brightness Distribution from Liquid Hydrogen Moderators at a High-Intensity Spallation Neutron Source－
  5. 5-5 Capturing of a Unique Spin Texture of a 4f Electron
    －Discovery of a Magnetic Skyrmion Lattice in the 4f Electron Magnet EuPtSi－
  6. 5-6 Towards Higher-Performance Steels
    －Elucidating the Microstructural Formation Mechanism via Electron and Neutron Beams－
  7. 5-7 Successful Observation of the Melting and Solidification Phenomena of Metal with a Time Resolution of One Millisecond
    －Contributing to the Advancement of Laser Welding Technology－
  8. 5-8 Compound Developed to Recognize Slight Size Differences of Rare-Earth Elements
    －Towards Efficient Recycling of Lanthanides－
  1. 6-1 Proposal of Innovative Nuclear Fuel Cycle Based on High Temperature Gas-Cooled Reactor
    －Reduction of Cooling Time of Potential Toxicity of Radioactive Waste－
  2. 6-2 Towards Implementation of Improved HTGRs
    －Conceptual Design of an Experimental HTGR for Steam Supply Based on an HTTR－
  3. 6-3 Improving the Fuel Safety of High Temperature Gas-Cooled Reactors during Severe Oxidation Accident
    －Fabrication of Oxidation-Resistant Fuel Elements for Oxygen Ingress Accidents－
  4. 6-4 Toward Load-Following, Demand-Dependent Operation of an HTGR
    －Confirming the Thermal Load Fluctuation Absorption Characteristics of an HTTR－
  5. 6-5 Improving Hydrogen Production Efficiency Using Innovative Technologies
    －High-Efficiency Process Design of the Thermochemical IS Process－
  6. 6-6 Reliability Improvements of Corrosion-Resistant Equipment for Hydrogen Production by the IS Process
    －Refined Quality Management of Glass-Lined Steel Material－
  7. 6-7 Membrane Makes IS Process Chemical Reaction Efficiently
    －Use of an Ion-Exchange Membrane to Reduce Water Permeation by Cross-Linking－
  1. 7-1 Examining the Behavior of Core Elements during a Strong Earthquake
    －Development of 3-Dimensional Reactor Core Group Vibration Analytical Model－
  2. 7-2 Clarifying the Discharge Behavior of Molten Core Materials
    －Simulated Experiments Using a Shallow Water Pool for Molten Core Discharge－
  3. 7-3 Uncertainty Analyses of MA Sample Irradiation Test Data
    －For Better Utilization of the Rare Data－
  4. 7-4 Development of a Long Life Fast Reactor Control Rod
    －Irradiation Behavior of a Sodium-Bonded Absorber Pin－
  5. 7-5 Advancing Microwave Heating Denitration Technology
    －Development of Particle Control Technology to Improve Powder Characteristics－
  1. 8-1 Simplification of the Analysis of Uranyl Ions in Radioactive Wastes
    －Development of an Analytical Method with Capillary Electrophoresis Using Novel Fluorescent Reagents－
  2. 8-2 Reducing the Generation of Uranium Waste
    －Decontaminating Metal Using Acidic Electrolytic Water－
  3. 8-3 Ensuring the Stability of Trench-Type Radioactive Waste Disposal Facilities
    －Examination of Waste Acceptance Criteria of Sand Filling to Reduce Voids in Waste Packages－
  4. 8-4 Improvement of Matching Method for Seepage Flow Analysis
    －Application of Inversion for Seepage Flow Analysis in Multi-Layered Earthen Cover－
  5. 8-5 Evaluating the Uncertainty of the Redox Potential in Groundwater
    －An Application Example Based on Monitoring Data of Water Quality in the Horonobe Area－
  6. 8-6 Estimating the Hydraulic Conductivity around a Gallery before Excavation
    －An Estimation Method Applying the Mean Stress Index－
  7. 8-7 Dating Calcium Carbonate Using a Micro-Scale Analytical Method
    －A Method for Tracing Prior Underground Water Environments－
  8. 8-8 Chemical Analysis and Identification of Many Mineral Grains
    －New Technique to Elucidate the Mountain Uplifting Process－
  9. 8-9 Unified Management of Repository Design Information
    －Development of a Design Support System for Geological Disposal Projects－
  10. 8-10 Realistic Modeling of Tracer Migration in Rock Fracture
    －Effects of Fine-Scale Surface Alterations on the Tracer Retention in Fractured Crystalline Rock－
  11. 8-11 Stabilization of Low-Level Radioactive Waste Solutions
    －Cement Solidification of Low-Level Radioactive Waste Solutions Containing Carbonates－
  12. 8-12 Investigation of Fuel-Cladding Materials for the Reprocessing of Spent Nuclear Fuel
    －Evaluation of the Nitric Acid Resistance of New Materials Preventing Severe-Accident Progression－
  13. 8-13 Predicting the Flow and Mixing Behavior in an Extractor
    －Simulating Fluidity, Dispersion, and Mass Transfer in a Centrifugal Contactor－
  1. 9-1 Acceleration of Plume Dispersion Model
    －Reduced-Communication Algorithm for GPU-Based Supercomputers－
  2. 9-2 Matrix Solvers for Multiphase CFD Simulations with One Hundred Billion Grids
    －Communication Avoiding Multigrid Methods－
  3. 9-3 Prediction of Laser Irradiation Condition in Laser Processing
    －Provision of Laser Irradiation Condition for Melting and Solidification Processing Using Computational Science Code SPLICE－
  4. 9-4 Modeling the Effects of Hydrogen on Metallic Materials
    －Spontaneous Separation of Aluminum Grain Boundaries by Hydrogen－
  5. 9-5 AI-Assisted Acceleration of Quantum Simulations
    －Analysis of Strongly Correlated Electron Systems with Sparse Modeling－
  1. 10-1 Nondestructive Assay of Nuclear Materials Using γ-rays
    －Development of Simulation Code for γ-ray Elastic Scattering－
  1. 1-1 How is Debris Distributed?
    －Evaluation of the Detailed Debris Distribution and Re-Criticality by Large-Scale Simulation－
  2. 1-2 Two Types of Insoluble Cesium Particles Emitted at the Early Stages of the Accident
    －Investigation of the Generation Process of Mainly Silicate Particles－
  3. 1-3 Chemical Reaction between Stainless Steel and Cesium
    －Estimation of the Cesium Distribution within the TEPCO?fs Fukushima Daiichi NPS－
  4. 1-4 Zirconium Hinders the Oxidative Dissolution of Nuclear Fuel
    －Effect of Zirconium Incorporation in Uranium Oxide upon Inhibiting Oxidative Dissolution－
  5. 1-5 Characterization of Waste Generated by Contaminated Water Treatment
    －Analysis of Carbonate Slurry－
  6. 1-6 Safe Long-Term Storage of Secondary Wastes after Decontamination of Radioactive Water
    －Evolution of Radiolysis Studies to Support Practical Issues in the Decommissioning of 1F－
  7. 1-7 Understanding the Radioactive-Contamination Situation Inside the TEPCO’s Fukushima Daiichi NPS Building
    －Development of 3D-Visualization Technology for Radioactive Substances－
  8. 1-8 Remote Laser-Sampling Technologies
    －Development of Concrete-Sampling Technologies Using High-Power Lasers－
  9. 1-9 Development of a Robot Simulator for Nuclear Decommissioning
    －Operator-Proficiency Training and Performance Evaluation of the Robot by Simulation－
  10. 1-10 Detection of Radionuclide Depth in Soil by Aerial Radiation Monitoring
    －Technology for Estimating the Vertical Distribution of Radionuclides in Soil Based on the γ-ray Spectrum－
  11. 1-11 Highly Accurate Measurement of Radiation-Dose Distributions
    －Realization of Highly Accurate Radiological Airborne Monitoring on Rugged Terrain－
  12. 1-12 How is Radiocesium Distributed in a Town?
    －Investigation of the Radiocesium Distribution in Residential Areas－
  13. 1-13 Prediction of Radiocesium Behavior in Upstream Catchment
    －Sediment and Radiocesium-Transport Simulation during Approximately Five Years Following the 1F Accident－
  14. 1-14 Research on the Distribution of 137Cs in Seabed Sediments
    －Relationship between the 137Cs Inventory and Seafloor Topography－
  15. 1-15 Prediction of the Dispersion of Radionuclides Released into the Ocean
    －Dispersion Simulation of Radionuclides from Coastal Regions to the Open Sea－
  16. 1-16 Determining the Conditions for Effective Forest Decontamination
    －Simulation of the Effect of Reducing Air-Dose Rate by Decontamination－
  17. 1-17 Nanoscale Visualization of Cesium Adsorption to Clay Minerals
    －Chemical Mapping Using Synchrotron-Radiation-Photoemission Electron Microscopy－
  18. 1-18 Strongest Cesium-Adsorption Site on Clay Minerals
    －Numerical Simulations of Cesium Adsorption on Microscopic Surface Structures－
  19. 1-19 Becoming Familiar with Research Related to Environmental Recovery in Fukushima
    －Development of a Comprehensive-Evaluation System and Clarification of Scientific Grounds and Insights－
  1. 2-1 Prediction of the Cooling Capability of a Superheated Reactor Core
    －Experiments for Modeling Post-Boiling Transition Heat Transfer－
  2. 2-2 Evaluation of Fuel Integrity during Loss-of-Coolant Accidents
    －Influence of Air Fraction in Steam during High-Temperature Oxidation of Fuel Cladding－
  3. 2-3 Evaluation of the Environmental Release of Radionuclide Material in a SA
    －Accident Analysis Considering Oxidation of BWR Control Material－
  4. 2-4 Evaluating Radiation Exposure Difference Inside and Outside a Vehicle
    －Development of a Vehicle Model for Radiation Transport Simulation and Its Application－
  5. 2-5 Evaluation of Confinement Performance at a Reprocessing Plant during Severe Accidents
    －Experiment to Clarify the Migration/Deposition Behavior of Volatile Radioactive Ruthenium－
  6. 2-6 Deducing the Origin of Nuclear Materials by Analyzing Uranium Particles in Environmental Samples
    －Determination of Chemical Forms and Isotope Ratios in Individual Uranium Particles for Nuclear Safeguards－
  1. 3-1 Capturing Various Nuclear Splits in Fission
    －Toward the Reduction of Radiotoxicity of Nuclear Waste－
  2. 3-2 Protection from Metal Toxicity by a Protein?
    －Binding of Heavy Elements to Soluble Glycoprotein on the Paramecium Cell Surface－
  3. 3-3 Seeing Hypernuclei by γ rays
    －Can Hidden “Strangeness” in Neutron Stars Be Disclosed?－
  4. 3-4 Unraveling the Mechanism of Strong Superconductivity in a Uranium Compound Exposed to a Magnetic Field
    －New Electronic State Revealed by High-Resolution Nuclear Magnetic Resonance Measurements at Cryogenic Temperatures－
  5. 3-5 Safer Memory Storage by “Antimagnets”
    －A New Way of Controlling Antiferromagnetic Magnetization－
  6. 3-6 Spin Current Power Generation
    －Magnon Density of States in Y3Fe5O12 Determined via Neutron Scattering－
  1. 4-1 Accuracy Improvement of Nuclear Data on Minor Actinides
    －Evaluation of the Thermal-Neutron-Capture Cross Section Using Resonance Structure－
  2. 4-2 Self-Healing of Ceramics in a Radiation Environment
    －Result of Using a New Method for Observing Ceramic Surfaces－
  3. 4-3 Computational Design of High-Toughness Alloys
    －Magnesium-Alloy Design from Electronic-Structure Calculations－
  4. 4-4 Toward Elucidation of Solvent Extraction Mechanism
    －Observation of Metal Ions at an Interface Using a Laser－
  5. 4-5 Elucidation of the Genetic-Transformation Process by Radiation
    －Role of Extremely Low-Energy Electrons below 1 eV－
  6. 4-6 Theoretical Estimation of the Therapeutic Effect of Boron Neutron Capture Therapy
    －Development of a Mathematical Model Useful for Drug-Discovery Research and Treatment Planning－
  7. 4-7 Radioactive-Material Behavior during a Severe Accident
    －Evaluation of the Release and Transport of Radioactive Materials in a Reactor－
  8. 4-8 Improving the Reliability of Nuclear-Characteristics Prediction for Accelerator-Driven Systems
    －Critical Experiment to Validate Nuclear-Data for Lead-Coolant on a Critical Assembly in the United States－
  9. 4-9 A New Technique for Extracting Low-Power Proton Beams with a Laser
    －Establishment of the Elemental Technology Required for the TEF－
  10. 4-10 Plant-Safety-Measurement Enhancement
    －A Study of Sheath Materials for Use on MI Cables during Severe Accidents－
  1. 5-1 High-Intensity Proton Acceleration Using a Broadband RF Cavity
    －Investigation of Beam Instability Caused by Higher Harmonics－
  2. 5-2 Elucidation of the Strengthening Mechanism of High-Strength Steels by Pulsed-Neutron Analysis
    －Dislocation Evaluation during Deformation of Lath Martensitic Steel－
  3. 5-3 Supplying Pulsed Neutron Beams with Narrow Width and Short Decay
    －Development of a Low-Activation Thermal-Neuron Absorber for Neutron-Beam-Pulse Shaping－
  4. 5-4 Establishment of a Novel Analysis Technique for High-Performance-Steel Development
    －Application of an Accelerator-Driven Compact Neutron Source in the Manufacturing Industry－
  5. 5-5 Characterization of Spin Arrangement by Neutron Transmission
    －For Observation under Extreme Environments and Mapping of Spin Arrangements－
  6. 5-6 Clarifying the Chemical State of Platinum-Group Elements in Borosilicate Glass
    －Advanced Analysis of Correlations between Constituent Elements Using Imaging XAFS－
  7. 5-7 Change of the Oxidation State of Fuel Cell Catalysts during Reactions
    －Surface Structure of Metal Nanoparticles Revealed by Synchrotron X-ray Absorption Spectroscopy－
  1. 6-1 Exploring High Temperature Gas-Cooled Reactor Safety
    －Accident Progression Analysis of HTGR during Extreme Seismic Events－
  2. 6-2 Environmental Burden Reduction by High Temperature Gas-Cooled Reactor
    －Study on Reducing Radioactive Waste by Utilizing the Characteristics of HTGR－
  3. 6-3 Enhancing the Safety of Plutonium Burner High Temperature Gas-Cooled Reactor
    －Test of ZrC Coating as an Oxygen Getter－
  4. 6-4 Development of a Passive Radiation Cooling System for High Temperature Gas-Cooled Reactors
    －Conceptual Development of a Decay Heat Removal Method during Accidents－
  5. 6-5 Improvement of Neutron-Startup-Source Exchange Work of the High Temperature Gas-Cooled Reactor
    －Downsizing of Transportation Container Adjusting with Exchange Processes－
  6. 6-6 Toward Efficient Hydrogen Production via the IS Process
    －Promotion of HI Decomposition by a Membrane Reactor－
  7. 6-7 Applicability Evaluation of Metallic Materials in Hydrogen Production by the IS Process
    －Corrosion Resistance of Nickel-Based Alloy in a Practical Gaseous HI Decomposition Environment－
  1. 7-1 Safety-Design Guidelines for Generation-IV Sodium-Cooled Fast Reactors
    －To Achieve Its Adoption into Leading-Edge Fast Reactors－
  2. 7-2 Evaluate the Mechanical Properties of MOX
    －Young’s Modulus Analyzed by the Sound Speeds of MOX Measured by the Ultrasound Method－
  3. 7-3 Evaluation on Cesium Behavior in a Fast-Reactor Fuel Element
    －Development of an Analytical Method for Fast-Reactor MOX-Fuel Elements－
  4. 7-4 Evaluation of the Irradiation Behavior of Fast-Reactor MOX Fuel
    －O/M-Ratio Dependence of Fuel Restructuring and Fuel Temperature－
  5. 7-5 Determining Inspections Necessary for Maintaining Fast Reactor Performance
    －Development and Standardization of a Determination Method for In-Service Inspection of Fast Reactors－
  6. 7-6 Advanced Inspection Technology for JSFR SG Tubes
    －Development of a Hybrid Eddy Current Sensor for Small Defects－
  7. 7-7 Evaluation of Chemical Reaction Behavior during Severe Accidents in Fast Reactors
    －Chemical Reaction Dynamics between Concretes and Sodium－
  1. 8-1 Integrated Evaluation of Radioactivity in Waste from Multiple Facilities
    －Study of a Common Evaluation Method for Radioactivity in Research Reactor Waste－
  2. 8-2 Ultratrace Analysis of Rare Earth Elements in Groundwater
    －Improvement of the Onsite Extraction Method for the Study of Underground Redox Conditions－
  3. 8-3 What Will Happen to Groundwater When Closing the Underground Drift?
    －World’s First On-Site Observation of Groundwater Chemistry in a Closure Drift－
  4. 8-4 Development of a Method to Infer Fault Connectivity
    －A New Ductility Index Including the Mechanical Properties of Rocks－
  5. 8-5 Accumulation of Heavy Metals in Biofilms in a Deep Subsurface Environment
    －Evaluation of Heavy Metal Sorption in Groundwater Interaction Systems of Microbes, Rocks, and Groundwater－
  6. 8-6 Characterization of Mass Transport Paths in Mudstone with a Fracture
    －Establishing an In Situ Tracer Test Method for Groundwater Saturated with Dissolved Gas－
  7. 8-7 Efficient Analysis of Rock Mineral Content Ratio
    －Modal Analysis Using X-ray Maps and Image Processing－
  8. 8-8 Transport of Radionuclides in Specific Surface Environments
    －Application of an Open Data Method to Assess Sediment Transport－
  9. 8-9 Vitrification Technology for Radioactive Elements
    －Search for an Appropriate Glass Medium－
  1. 9-1 Challenges of Solid-State Physics with AI Technology
    －Machine Learning Accelerates Quantum Simulations－
  2. 9-2 Elucidation of Embrittlement of Steels from Analysis of Atomic-Diffusion Behavior
    －Evaluation of the Diffusion Coefficient by Kinetic Monte Carlo Simulation Based on First-Principles Calculation－
  3. 9-3 Proposing a New Standard for Radiation Damage to Nuclear Materials
    －Establishing a Radiation-Damage-Evaluation Formula Based on Numerical Simulations－
  4. 9-4 Development of Visualization Technology for Large-Scale Simulation at Runtime
    －In-Situ Visualization Using Particle-Based Volume Rendering－
  1. 10-1 Development of a New Method for Age Determination
    －Reduction of Analytical Time Using the Secular Equilibrium State in a Sample－
  1. 1-1 Observation of Core Melting and Relocation Behavior under Severe-Accident Conditions
    －Plasma-Heating Tests with a Simulated Fuel Assembly－
  2. 1-2 Predicting the Location of Melt Leakage from the Reactor Pressure Vessel during Severe Accidents
    －Development of a Failure-Evaluation Method Based on Thermal-Hydraulics and Structural Analyses－
  3. 1-3 Toward Estimating Characteristics of Radioactive Material Released in Severe Accidents
    －Experimental and Analytical Technologies for Evaluating Fission Product Chemistry in a Reactor－
  4. 1-4 Thermodynamic Estimation of Fuel Debris Characteristics
    －Thermodynamic Evaluation of High-Temperature-Reaction Products between Molten Core and Concrete－
  5. 1-5 Can Fuel Debris be Retrieved without Water?
    －Development of a Numerical-Simulation Method for Air Cooling of Fuel Debris－
  6. 1-6 Investigating the Effect of Seawater and Concrete Components upon Nuclear-Fuel-Reprocessing-Plant Materials
    －Effect of Sulfate Ions upon Corrosion of a Highly Active Liquid-Waste Tank－
  7. 1-7 Estimation of the Amount of Radioactivity in Water-Treatment Waste
    －Calculation of Radionuclide Concentration in Contaminated Water－
  8. 1-8 Development of a Small, Portable Position-Sensitive Alpha-Particle Detector
    －Direct Measurement of Plutonium Contamination in Narrow Spaces of Solid-Waste Material and Equipment－
  9. 1-9 Study of the Contamination State inside the Reactor Building
    －Detailed Radiochemical Analysis to Accelerate Disposal of Waste－
  10. 1-10 Development of an Analytical Method to Determine 93Zr, 94Nb, and 93Mo Concentrations in Contaminated Water and Rubble Waste
    －Radiochemical Separation of Difficult-to-Measure Nuclides－
  11. 1-11 Development of a Test Method for Remotely Operated Robots for Decommissioning
    －Design of Testing Fields for Robot-Performance Evaluation and Operator-Proficiency Training－
  12. 1-12 Fiber Detector for Monitoring of Contaminated Water
    －Demonstration Experiment at the TEPCO’s Fukushima Daiichi NPS－
  13. 1-13 Estimation of Doses to Residents with Consideration of Behavioral Patterns
    －Is Decontamination of Residential Areas Based on a Guide Value of 0.23 µSv/h Effective?－
  14. 1-14 How Long Does Radiocesium Remain in Forest-Surface Litter?
    －Radiocesium Transfer from Litter to Mineral Soil in Two Forest Types－
  15. 1-15 Mechanism of Vertical Migration of Radiocesium into Soils
    －Effect of Sorption Kinetics upon Vertical Migration of Radiocesium into Soils－
  16. 1-16 Redeposition Mechanism of Radiocesium on River Flood Plains
    －Heterogeneous Distribution of Radiocesium Depending on Weather, Topography and Vegetation－
  17. 1-17 Prediction of the Amount of Radiocesium Discharge during Typhoons and Heavy-Rainfall Events
    －Simulation of the Amount of Radiocesium Discharge between Several River Basins－
  18. 1-18 Reproduction of the Soil using Salt
    －Synchrotron X-rays Reveal the Mechanism of Cesium Removal from Soil－
  19. 1-19 Observation of Atomic-Scale Edge Structure via Supercomputers
    －Towards an Understanding of the High Cesium Affinity of Clay Minerals－
  20. 1-20 Prevention of Radioactive Cesium Accumulation in Shiitake Mushrooms Cultured with Contaminated Wood Logs
    －Reduction of Cesium Absorption using Minerals－
  1. 2-1 Estimating Hydrogen-Gas Behavior during Nuclear Power Plant Accidents
    －Influence of Mesh Shape upon Computational Fluid Dynamics Analysis of Buoyant Flows－
  2. 2-2 Evaluating Molten-Core-Debris Formation in Reactor Containment Vessels
    －Evaluation of Molten-Core Coolability in Severe Accidents－
  3. 2-3 Refinement of Crack Growth Evaluation in the Reactor Internals of Light Water Reactors
    －Analyses of Locally Deformed Structures and Strain in Highly Irradiated Stainless Steels－
  4. 2-4 Deterioration Rate of Buffer Material in Geological-Disposal Sites
    －Alteration Rate of Compacted Montmorillonite under Highly Alkaline Conditions－
  5. 2-5 Evaluating the Effect of Seismic Activity upon Geological Disposal
    －Evaluation of the Influence of Splay-Fault Growth upon Groundwater Flow around a Geological-Disposal System－
  6. 2-6 Determination of Plutonium-Isotope Ratios in Individual U/Pu Mixed Particles
    －Novel Approach using Alpha and Mass Spectrometry for Nuclear Non-Proliferation－
  1. 3-1 New Experimental Method for Obtaining Nuclear-Fission Data
    －Opening-Up Fission Studies for Neutron-Rich Nuclei－
  2. 3-2 A New Form of Atomic Nuclei with a “Strange Particle”
    －An Antikaon and Two Nucleons Make a Bound State through the Strong Interaction－
  3. 3-3 Magnetic Order of Non-Magnetic Ions
    －Theoretical Investigation of Higher-Order Magnetic Order of Non-Kramers Ions－
  4. 3-4 High-Speed Rotation Turns an Ordinary Metal into a Magnet
    －Exploring the Relationship between Magnetism and Rotation that Fascinated Einstein－
  5. 3-5 Asymmetric Structure of the New “Germanene” Material
    －Possible New Germanene Properties－
  1. 4-1 Prevention of Severe-Accident Progression by Delaying Core Overheating and Melting
    －Development of FEMAXI-ATF Code for Accident-Tolerant Fuel-Behavior Analysis－
  2. 4-2 Efficient Partition of Nuclides in High-Level Waste
    －High-Efficiency Separation of Americium and Curium－
  3. 4-3 Reliability Evaluation of Nuclear Data Required for Core Design of Nuclear Transmutation Systems
    －Verification of Trans-Uranium (TRU) Cross-Sections Based on Critical Experiments using FCA－
  4. 4-4 Real-Time Measurement of Heavy-Liquid-Metal Flow under a Severe Environment
    －Development of an Ultrasonic Flowmeter for a Lead-Bismuth Target－
  5. 4-5 Interface of Nuclear Data and Transport Codes
    －Development of Nuclear Data Processing System FRENDY－
  6. 4-6 Research on the Material-Degradation Behavior by Radiolytic-Hydrogen Absorption
    －Hydrogen-Absorption Behavior on Zirconium under γ-ray Irradiation－
  7. 4-7 Predicting Mechanical Properties of Alloys
    －Computational Approach for Modeling the Strengthening/Softening Mechanism－
  8. 4-8 Quantitation of the Difficult-to-Measure Nuclide Palladium-107
    －Measurement of Palladium Obtained by Laser Irradiation of Spent Nuclear Fuel－
  9. 4-9 Forecast of Radionuclide Dispersion in the Ocean
    －Development of an Emergency-Assessment System for Marine-Environmental Radioactivity－
  10. 4-10 Development of Neutron Calibration Fields for Improving the Reliability of Neutron-Dose Estimation
    －Moderated Neutron Calibration Fields Considering Energy Distributions in Actual Workplaces－
  1. 5-1 Magnetic-Structure Analysis of a Highly Neutron-Absorbent Material with Pulsed-Neutron Diffraction
    －Magnetic Structure of EuGa4 Studied by Single-Crystal Neutron Diffraction－
  2. 5-2 Towards a Comprehensive Understanding of the Unique Magnetic Properties of Layered Systems
    －An Application of Polarized Neutron Scattering under Grazing-Incidence Geometry to Analysis of In-Plane Magnetic Structure－
  3. 5-3 Realization of High-Intensity Proton Beams
    －Beam-Instability Issues and the Measure at the 3-GeV RCS in J-PARC－
  4. 5-4 Exploring the Structural Materials Frontier using Neutron Diffraction
    －Development of the Bulk Texture Measurement Technique at the Rapidest Level－
  5. 5-5 Nanoscopic-Structural Investigation of Nanoparticles for Drug-Delivery Carriers
    －Small-Angle Neutron Scattering Reveals the Internal Structure of Nanogels－
  6. 5-6 Aiming for the Development of Stronger Stainless Steel
    －First Observation of an Intermediate ε-phase at Room Temperature using High-Intensity Synchrotron Radiation－
  7. 5-7 Electronic Structure of Actinide Compounds Studied by Synchrotron Radiation
    －Electronic Structures of Uranium Compounds that Show the Coexistence of Superconductivity and Magnetism－
  1. 6-1 Toward a Demonstration of the HTGR Cogeneration System
    －Completion of Component Design and Preliminary Safety Assessment for the HTTR-GT/H2 Plant－
  2. 6-2 Development of High-Temperature Equipment for Heat Utilization of a High-Temperature Gas Furnace
    －Proposal for a Low-Cost, Long-Lived Intermediate Heat Exchanger－
  3. 6-3 Toward Practical Load-Following Operation of HTGRs Connected to Heat-Application Systems
    －Elucidation of Thermal-Load-Fluctuation Absorption at Various Coolant Pressures－
  4. 6-4 Safety Enhancement of High-Temperature Gas-Cooled Reactors
    －Nuclear and Thermal Design of an Oxidation-Resistant Fuel-Loaded Reactor Core－
  5. 6-5 R&D on CO2-Free H2 Production by the IS Process
    －Progress from Lab Stage to Industrial-Material-Facility Stage－
  6. 6-6 Clarifying the Core Temperature in High-Temperature Gas-Cooled Reactors
    －Development of Measurement Technology Based on Melt Wires for Control-Rod Temperature to Estimate Core Temperature－
  1. 7-1 Sophisticated Structural-Integrity Assessment of Fast-Reactor Components
    －A Proposal of Procedure for Assessing Leaks before Breakage of Fast-Reactor Pipes－
  2. 7-2 Development of a Thermal-Hydraulic-Evaluation Method for a Straight-Tube Steam Generator
    －Establishing a Three-Dimensional Simulation Model and Comparing it with Test Data－
  3. 7-3 Improvement of Maintenance Technology for Sodium-Cooled Fast Reactors
    －Development of a Visual-Inspection Device under Opaque Sodium－
  4. 7-4 Progress in Reactor Modeling during Natural-Circulation Cooling
    －Validation of a Reactor Analytical Model using Measured Data－
  5. 7-5 Advancing the Separation Process for Spent Nuclear Fuel Reprocessing
    －Development of a Sludge-Cleaning Method in a Centrifugal Contactor－
  1. 8-1 Quantifying the Radioactivity of Waste Products
    －Accuracy Improvement of a Quantitative Method Focused on Scattering γ-rays－
  2. 8-2 Radioactivity-Confirmation Method for the Disposal of Low-Level Waste
    －Evaluation Method to Determine the Radioactivity Concentration in Radioactive Waste Generated from Post-Irradiation Examination Facilities－
  3. 8-3 Understanding the Self-Sealing Function of the Underground Environment
    －Study of the Long-Term Behavior of Hydrogeological Structures Related to Faulting－
  4. 8-4 Micropores Retarding Mass Transport in Granitic Rock
    －Visualization and Observation of Matrix-Diffusion Pathways－
  5. 8-5 Demonstration of Geological Disposal Technology in a Real Underground Environment
    －Technological Development for an In situ Experiment to Confirm the Performance of an Engineered Barrier System at the Horonobe Underground Research Laboratory (URL)－
  6. 8-6 Investigation of the Fault Distribution in Sedimentary Rocks
    －Relationship between Faults Oriented Parallel and Oblique to Bedding in Neogene Massive Siliceous Mudstones－
  7. 8-7 Dating of Minerals in Rocks
    －Technical Development of a Rapid CHIME Dating Procedure－
  8. 8-8 Mechanistic Modeling of Nuclide Migration in Rock
    －Clay-Based Modeling Approaches for Diffusion and Sorption in Mudstone－
  9. 8-9 Evaluation of the Long-Term Mechanical Behavior of a TRU Waste Repository
    －Development of a Mechanical Analysis Method Considering the Chemical Evolution of Engineered Barrier Materials－
  10. 8-10 Improvement of the Uncertainty and Rapidity of the Measurement Technique for a Plutonium Nitrate Solution Sample
    －Improvement of Neutron Nondestructive Assay－
  11. 8-11 Understanding the Characteristics of Insoluble Sludge in the Reprocessing of Fast Reactor Fuels
    －Evaluating the Characteristics of Insoluble Sludge from the Dissolution of Irradiated Fast Reactor Fuel－
  1. 9-1 Acceleration-Flow Analysis in a Nuclear Reactor
    －Development of Massively Parallel Communication-Avoiding Matrix Solvers－
  2. 9-2 Development of a Low-Power-Consumption Computing Technology Based on Accelerators
    －Optimization of Nuclear-Fluid-Simulation Kernels on Accelerators－
  3. 9-3 High-Temperature Properties of Nuclear-Fuel Materials
    －First-Principles Molecular-Dynamics Simulation of Thorium Dioxide－
  4. 9-4 Solving the Mystery of Irradiation-Resistant Alloys
    －Simulation of Interstitial Atoms’ Migration Based on First-Principles Calculation－
  1. 10-1 Toward Enhancement of Monitoring Capability for Nuclear Tests
    －Evaluating the Impact of MIPF on Observational Results at CTBT Radionuclide Stations－
  1. 1-1 Evaluation of the Temperature Range of Melted Debris in the Reactor at the Nuclear Accident
    －The Influences of Pu and Zr upon the Melting Temperatures of (U, Pu, Zr)O2－
  2. 1-2 Laser Remote Analysis of Nuclear Fuel Debris
    －Evaluation of Uranium Spectra by Laser Induced Breakdown Spectroscopy (LIBS)－
  3. 1-3 Development of a Cutting Technique for Core-Structural Materials and Fuel Debris
    －Cutting and Crushing of Core-Structural Materials and Fuel Debris with a Plasma Jet－
  4. 1-4 Elucidation of the Core-Meltdown Procedure in Severe Accidents using Supercomputers
    －Development of A Numerical Simulation Method for Evaluating the Influences of Chemical Reactions of Core Materials－
  5. 1-5 Behavior of Radioactive Cesium Deposited in the Nuclear Reactor
    －Investigation of Cesium-Deposition Behavior onto Stainless Steel－
  6. 1-6 Integrity Evaluation of a Storage Vessel Containing Spent Cesium Adsorption Material
    －Investigating the Possibility of Localized Corrosion of the Vessel Material under Irradiation－
  7. 1-7 Toward the Recovery of Uranium from Fuel Debris
    －Development of a Chlorination Method for Slightly Soluble Components－
  8. 1-8 Visualization of the Radioactive-Cesium Distribution using a New Compton Camera Mounted on an Unmanned Helicopter
    －Field Test of the Ce:Gd3(Al,Ga)5O12 (GAGG) Scintillator Compton Camera－
  9. 1-9 Accurate Measurement and Evaluation of Environmental Dose Rates in Air
    －Dose-Rate Evaluation in the Environment using Monte Carlo Simulation－
  10. 1-10 Evaluating Air-Dose Rates due to Radiocesium using a Supercomputer
    －Calculation of Air-Dose Rates from Radioactive Cesium Distributed in the Ground－
  11. 1-11 Transfer of Radioactive Cesium in the Hardwood Forest
    －Study of Radioactive-Cesium-Transport Behavior in Trees in a Forest－
  12. 1-12 Spatial Variation in Radioactive-Cesium Deposition Caused by Topographical Factors
    －Detailed Examination of the Air-Dose Rate in a Mountainous Forest Catchment－
  13. 1-13 Environmental Behavior of a Minute Amount of Radioactive Cesium
    －Cs-Sorption/Desorption Behavior of Clay Minerals Considering the Actual Contamination Condition in Fukushima－
  14. 1-14 Elucidating the Adsorption States of Cesium in Clay Minerals
    －Analysis via First-Principles-Based Simulations－
  15. 1-15 New Technology for Suppressing Cesium Migration from Forests
    －Mild Regeneration of Village Forests with Polymers and Clay－
  16. 1-16 Safety of Burial of Contaminated Soil at Public Parks
    －In situ Experiments on the Migration of Radioactive Cesium from the Buried Soil－
  17. 1-17 Realization of Automatic Analysis of Radioactivity in Samples
    －Development of an Automatic Analysis System for Strontium-90 in an Environmental Sample－
  1. 2-1 Prediction of Hydrogen Behavior in a Reactor Containment Vessel during a Severe Accident
    －Thermal-Hydraulic Safety Research on Reactor Containment Vessels by the ROSA-SA Project－
  2. 2-2 Evaluating the Degree of Deformation of the Fuel-Cladding Tube during Loss-of-Coolant Accidents
    －Effect of Oxidation and Crystal-Phase Condition of the Cladding Tube－
  3. 2-3 Chemistry of Fission Products during Severe Accidents
    －Effect of the Chemical Form of the Fission Products upon the pH of Coolant Water－
  4. 2-4 A New Attempt to Compare Radiation Risks with the Other Health Risks
    －Radiation-Health-Risk Estimation in Disability-Adjusted Life Years (DALY)－
  5. 2-5 Acquisition of Data Required for Severe-Accident Evaluation in a Reprocessing Plant
    －Understanding the Release Characteristics of Ruthenium from Highly Active Liquid Waste during a Drying Step－
  6. 2-6 Evaluation of the Criticality Characteristics of Fuel Debris
    －Study of the Critical Experiment using the Modified STACY－
  1. 3-1 Reentrant Superconductivity Induced by a Strong Magnetic Field
    －New Functional Properties of Uranium Compounds Controlled by a Magnetic Field－
  2. 3-2 Electrical Generation from Liquid-Metal Flow
    －Discovery of a New Principle of Electrical Generation via Electron-Spin Motion－
  3. 3-3 Positron Diffraction Technique Reveals an Interface Structure between Graphene and Metal Substrates
    －Elements in Substrate Change the Bonding Character of Graphene－
  4. 3-4 A ?gStrange Particle?h Breaks the Charge Symmetry of a Nucleus
    －Successful Measurement of the Energy Levels of a Helium Hypernucleus－
  5. 3-5 Exploring the Mystery of Neutrino Masses with Nuclear Physics
    －High-Precision Calculation of ???? Decay using the K Supercomputer－
  1. 4-1 Pursuit of Accurate Nuclear-Reaction Cross-Sections in the Resonant Region
    －Synergy between Nuclear-Data Measurement and Theory－
  2. 4-2 Nuclear-Material Quantification by Observation of Transmitted Neutrons
    －A Non-Destructive Assay Technique for Measurement of Complex Nuclear Fuel using a Neutron-Resonance Reaction－
  3. 4-3 Measurement of the Corrosive Environment in High-Temperature, High-Pressure Water within Light Water Reactors
    －Development of an Electrochemical Measuring Technique and Evaluation of the Corrosive Condition in High-Temperature Pure Water－
  4. 4-4 Predicting the Property Changes in Nuclear Reactor Materials
    －Understanding the Hardening Mechanism owing to Nano-Sized Defects: Molecular Dynamics Simulation－
  5. 4-5 Exploring the Valence of Uranium by Luminescence
    －Time-Resolved Laser-Induced Fluorescence Spectroscopy for Short-Lived Species－
  6. 4-6 Preparation of a Micro-Sized Solid-Phase Extraction Cartridge
    －Separation Cartridge Designed for Trace Analysis of Difficult-to-Measure Nuclides－
  7. 4-7 Understanding the Migration Behavior of Transuranic Elements from Forests to Rivers
    －Migration Behavior Research using Rare Earth Elements that Exhibit Chemical Similarity to Transuranic Elements－
  8. 4-8 Toward Detailed Prediction of the Radiation Damage to Structural Materials in Accelerators
    －Development of a Cryogenic Irradiation Device for Validation of the Radiation-Damage Model－
  9. 4-9 Visualization of Water-Steam Fractions under High-Pressure and High-Temperature Conditions in Reactor Cores
    －Development of Technology for the Measurement of Steam Volumetric Fractions in Fuel Assemblies with Wire-Mesh Sensors－
  10. 4-10 Prevention of Severe-Accident Progression by Delaying Core Overheating and Melting
    －Development of Fuel-Cladding Materials with High Resistance to Oxidation－
  11. 4-11 Investigation of a New Transmutation System Concept
    －Implementation of an Analysis Code for an Accelerator-Driven System with a Subcriticality Adjustment Mechanism－
  12. 4-12 Recovery of Valuable Rare Metals from High-Level Radioactive Waste
    －Separation of Rhodium with Ion-Exchange Resin－
  13. 4-13 Toward the Establishment of a Method for Treating MA Transmutation Fuels
    －Development of the Technology for Pyrochemical Treatment of MA Nitride Fuel－
  1. 5-1 Realization of High-Accuracy Orbit Control of a High-Intensity Proton Beam
    －Development of a New Pulsed Power Supply for Eliminating Current Ripple－
  2. 5-2 A New Tuning Apparatus for High-Intensity Beams in a Linac
    －Beam-Phase-Distribution Measurement for Loss Reduction－
  3. 5-3 Successful Impact Mitigation with Microbubbles in Liquid Metal
    －Development of a Microbubble Generator in Mercury for Realizing the Most Intense Spallation Neutron Source in the World－
  4. 5-4 Opening up a New Frontier of Material Science using Single-Crystal Neutron Diffraction
    －Development of the Extreme Environment Single Crystal Diffractometer SENJU－
  5. 5-5 Probing Novel Characteristics of Unconventional Superconductors via Neutron Scattering under a Magnetic Field
    －Magnetic-Field-Enhanced Antiferromagnetism in Unconventional Superconductors－
  6. 5-6 Elucidation of the Selective Separation of Cesium by Small-Angle Neutron Scattering
    －Toward Selective Separation of Cesium using a ??-d Hybrid Orbital－
  7. 5-7 Electric Power Generation by Temperature Variation
    －Observation of Ferroelectric Materials under Power Generation using Synchrotron X-ray Diffraction－
  8. 5-8 Unmasking the Ferromagnetism in Magnetically-Doped Topological Insulators
    －Toward Ultra-Low Power-Consumption Spintronic Devices－
  9. 5-9 Nondestructive Three-Dimensional Elemental Analysis using an Ion Microbeam
    －Development of Particle-Induced X-ray-Emission Tomography－
  10. 5-10 The Challenge of Realizing Unexplored Super-Strong Electromagnetic Fields with a Laser
    －J-KAREN-P Laser Development－
  11. 5-11 Dual Treatment and Diagnosis Role Played by Simultaneous Emission of ??- and ??-rays
    －Production of Highly Purified Lutetium-177 for Radioimmunotherapy－
  12. 5-12 Elucidation of the Reaction Mechanism of an Anti-Cancer Drug at the Atomic Level
    －Precise Structural Analysis of a Drug?fs Target Protein using Synchrotron X-ray Radiation－
  13. 5-13 Toward Advancement of Heavy-Particle Cancer Therapy
    －Successful Development a New Radial Dose-Simulation Model－
  14. 5-14 Which Liver-Sashimi was Treated by Radiation?
    －Development of a Method to Distinguish Disinfected Liver－
  15. 5-15 A Polymer-Electrolyte-Membrane Fuel Cell with the World?fs Highest Power Density
    －Preparation of Polymer-Electrolyte Membranes by Radiation-Induced Graft Polymerization－
  16. 5-16 Toward the Realization of Quantum-Information Communication and Quantum Computing
    －Exploring Single-Photon Sources in Silicon Carbide－
  17. 5-17 Isotope Separation Utilizing Control of Molecular Rotation
    －An Isotope-Separation Method Effective for Heavy Isotopes－
  18. 5-18 A Quantitative Liquid-Analysis Method using Laser-Induced Plasma-Emission Light
    －A Highly Sensitive In situ Liquid-Analysis Technique under Severe Environments－
  19. 5-19 Real-Time Observation of Lattice Deformation in Nitride Semiconductors
    －Proposal for a New Lattice-Deformation Model that Defies Conventional Theory－
  1. 6-1 Development of International Safety Standards for Commercial HTGRs
    －Safety Requirements for the Design of HTGRs Based on the Inherent Safety Features Demonstrated by HTTR－
  2. 6-2 Toward Enhancing the Safety of Plutonium-Burner High Temperature Gas-Cooled Reactors
    －Prevention of Internal Gas-Pressure Failure of Fuel Particles Coated by Oxygen Getters－
  3. 6-3 Development of Oxidation-Resistant Graphite Materials for High Temperature Gas-Cooled Reactor Cores
    －Collaborative Study with the Institute of Nuclear Physics in Kazakhstan－
  4. 6-4 Investigation of the Process Conditions of Inhibition Reactions for Thermal-Efficiency Improvement
    －Effects of Impurity Contamination in an HI Concentrator－
  5. 6-5 Demonstration of Hydrogen-Cogeneration Technology using the HTTR
    －Designing the Helium Gas Turbine to Enable an Operability-Demonstration Test－
  6. 6-6 Proving the Seismic Integrity of the High-Temperature Gas-Cooled Reactor
    －Integrity Confirmation of Graphite Components by Seismic Evaluation and Visual Inspection－
  1. 7-1 Leading the World in Safety with the Next-Generation Sodium-Cooled Fast Reactor
    －Development and Standardization of Safety Design Criteria and Safety Design Guidelines－
  2. 7-2 Fast-Reactor-Core Design for Enhanced Radioactive-Waste Reduction
    －Harmonizing Safety and Nuclear Transmutation－
  3. 7-3 Improving Fast Reactor Safety
    －Experimental Confirmation of Fuel-Subassembly Melt and Discharge Behavior－
  4. 7-4 Clarification of the Wastage Phenomena of the Heat-Transfer Tubes of a Steam Generator in a Sodium-Cooled Fast Reactor
    －Evaluation on Corrosion Behavior with High-Temperature Sodium Hydroxide Flow－
  5. 7-5 The Effect of Am upon the Themophysical Properties of MA-MOX Fuel
    －The Relationship between Oxygen Potential and the O/M Ratio of (Pu0.928Am0.072)O2-x－
  6. 7-6 Dating of Crush-Zone Slip Episodes under a Subsurface High-Temperature Condition
    －Insights from Thermal-History Analyses Based on the Fission-Track Dating Method－
  1. 8-1 The Rapid and Precise Large-Scale Classification of Waste Drums
    －Feasibility Study on the Application of Machine Learning to Large Datasets for Rapid Classification－
  2. 8-2 Removal of Nitrate Salts from Bituminized Waste Products
    －Development of a Technology to Reduce the Impact of Nitrate Salts upon the Disposal Environment－
  3. 8-3 Toward Radioactive-Waste Conditioning Suitable for Near-Surface Disposal
    －Study on Standards Concerning a Solidification Method by using Mortar－
  4. 8-4 Influence of Distant Earthquakes upon Groundwater Flow
    －A Case Study in the Tono Area－
  5. 8-5 Estimation of Underground Density Structure
    －Development of a Technique to Estimate Underground Density Structure using Cosmic-Ray Muons－
  6. 8-6 Time History of Hydraulic Diffusivity Related to URL Excavation
    －A Poroelastic Analysis of Groundwater-Pressure Response to Atmospheric Loading－
  7. 8-7 Technology for Long-Term Monitoring of Damage around a Shaft
    －Monitoring the Excavation-Damaged Zone using Optical-Fiber Sensors－
  8. 8-8 Powerful Tools for Dating of Sediments
    －Development of High-Accuracy Analysis for Volcanic Glass Shards－
  9. 8-9 Assessment of the Effect of Geological Disposal upon Human Beings
    －Development of a Modeling Method for Biosphere Assessment Corresponding to Surface-Environmental Condition－
  10. 8-10 Various Parameter Settings upon Radionuclide Release
    －Review of the Release Behavior of Radionuclides for Spent-Fuel Disposal－
  11. 8-11 In Microwave Ovens, the Height of the Heating Specimen Changes the Ease of Warming
    －Heating Efficiency of the Nitric Acid by the Microwave－
  1. 9-1 Controlling Robots in a Radiation Environment
    －Using a Robot Vision-Based System to Position a Manipulator in a Fusion Reactor－
  2. 9-2 Manufacturing Superconducting Coils with High Accuracy
    －Establishing a Manufacturing Method for High-Circularity Superconducting Coils to Reduce the Error Magnetic Field－
  3. 9-3 Measurement of Magnetic Fluctuation of Fusion Plasmas
    －Development of Simple, High-Performance Magnetic Sensors－
  4. 9-4 Improving the Estimation Accuracy of Plasma Shape
    －Optimizing the Predictive Accuracy of the Plasma-Shape-Estimation System－
  5. 9-5 Toward Safe Operation of Nuclear Fusion Reactors
    －Discovery of a New Magnetohydromagnetic Instability that Causes Disruptive Events in Fusion Plasmas－
  6. 9-6 Confining Tritium in a Fusion Facility
    －A Catalytic-Reactor Design that Ensures Tritium Oxidation under All Possible Conditions－
  7. 9-7 Achievement of a Prototype-Accelerator-Performance Goal for the International Fusion Material Irradiation Facility (IFMIF)
    －Successful Injector-Beam Acceleration of the High-Current Deuterium Accelerator－
  8. 9-8 Management Scenario for Radioactive Wastes with Consideration of Public Acceptance of a Fusion Reactor
    －Study on Volume Reduction of Radioactive Wastes for a Fusion Reactor－
  9. 9-9 Development of Highly Efficient Neutron-Multiplier Materials for Early Realization of a DEMO Reactor
    －Research on Ternary Advanced Neutron Multipliers－
  1. 10-1 Advancement of Seismic-Response-Simulation Techniques for Nuclear Facilities
    －Vibration Simulation of a Nuclear Facility Building using a Three-Dimensional Vibration Simulator－
  2. 10-2 Determination of the Thermal Properties of Nuclear Fuels through Numerical Simulation
    －First-Principles Calculations of the Heat Capacity of Plutonium Dioxide－
  3. 10-3 Quest for Light Metals with Good Formability
    －A Novel Deformation Mechanism in Hexagonal Metals Revealed by Quantum Calculations－
  4. 10-4 Simulation Technology for Long-Time-Scale Analyses of Fusion Plasmas
    －Progress Toward Multi-Time-Scale Analyses－
  1. 11-1 Estimating the Production Date of Nuclear Material
    －Round-Robin Uranium-Age Dating for Nuclear Forensics－
  1. 1-1 Changes in Ambient Dose-Equivalent Rates Dependent on Land Use
    －Evaluation of Ecological Half-Lives for Decreasing Trends of Ambient Dose-Equivalent Rates－
  2. 1-2 Predicting the Doses to Residents Exposed to Radiations from Radioactive Cesium
    －Calculation of Age-Dependent Dose Conversion Coefficients for External Exposure－
  3. 1-3 Application of Lichens for the Record of Fukushima Fallout
    －A Potential Indicator for the Estimation of Initial Fallout Amount－
  4. 1-4 Efficient In situ Pre-Concentration of Strontium from Water Samples using Ion Exchange Resin
    －Development of Low-Level Radiostrontium Analysis in a Freshwater Sample－
  5. 1-5 Investigation of the Concentrations of Radionuclides in Seabed Sediments
    －The Spatial Distribution of Radionuclides in Seabed Sediments off the Ibaraki Coast－
  6. 1-6 Prediction and Visualization of the Decontamination Effect
    －Support for Decontamination Projects in Fukushima using the Restoration Support System for the Environment, “RESET”－
  7. 1-7 Investigation of the Mechanism of Cesium Adsorption into the Soil using a Supercomputer
    －Singular Adsorption of Cesium Revealed by First Principles Calculations－
  8. 1-8 Selective Adsorption of Radioactive Cesium onto Weathered Biotite
    －Successive Adsorption Mechanism of Cesium like “Domino Toppling”－
  9. 1-9 Removal of 137Cs from Sewage Sludge Ash by Dissolving Iron Oxide
    －Success in Removing 137Cs Efficiently through Elucidation of the Chemical States of 137Cs－
  10. 1-10 Evaluation of the Integrity of a Fuel Cladding Tube after Seawater Injection
    －Investigation of the Pitting Potential－
  11. 1-11 Integrity Assessment of a Fuel Assembly
    －Mechanical Property-Evaluation of a Fuel Cladding Tube Immersed in Seawater－
  12. 1-12 Evaluation of the Mechanical Properties of the Fuel Debris
    －Relationship between Fuel Debris and the Cladding Tube Components－
  13. 1-13 How do Microscopic Particles of Debris Change in Water?
    －To Understand the Chemical Effects of Hydrogen Peroxide and Boric Acid－
  14. 1-14 Investigating the Effects of Seawater on the Cooling Performance of a Reactor Core
    －Evaluation of the Thermal-Hydraulic Behavior of Seawater using a Model Fuel Rod－
  15. 1-15 Calculation of the Melting Behavior of Fuel Rods in Severe Accidents
    －Development of a Numerical Method Based on the Particle Method－
  16. 1-16 Estimation of the Failure Time and Location of the Pressure Vessel Lower Head in Severe Accidents
    －Development of Failure Evaluation Methods for the Pressure Vessel Lower Head－
  17. 1-17 Estimation of the Failure Time and Location of the Pressure Vessel Lower Head in Severe Accidents
    －High-Temperature Creep Test and Investigation of Creep Constitutive Laws－
  18. 1-18 Prediction of the Characteristics of Radioactive Materials Released from Nuclear Fuel during Nuclear Power Plant Accidents
    －Evaluation of the Effects of Boron Released from BWR Control Rods on the Chemical Behavior of Fission Products－
  19. 1-19 Accurate Estimation of the Amount of Radioactivity in Accident Waste
    －Estimation Method for the Samples and Nuclides that are Difficult to Analyze－
  20. 1-20 Safe Storage of Spent Cs-Adsorbents after Decontamination of Radioactive Water
    －Estimation of H2-Generation in Spent Vessels from the Latest “Small-Scale Experiments”－
  1. 2-1 Investigation of the Fracture Resistance of Zircaloy Cladding under a Post-LOCA Condition
    －Evaluation of Ruptured and Quenched Cladding by Four-Point-Bend Tests－
  2. 2-2 Exploring Latent Uncertainties and Influential Factors in Severe Accident Analysis
    －Development of an Integrated Approach to Uncertainty and Sensitivity Analyses for Source Terms－
  3. 2-3 Evaluation of the Precautionary Action Zone for a Nuclear Emergency
    －Development of an Evaluation Method using a Probabilistic Consequence Analysis－
  4. 2-4 Improvement of Severe Accident Assessment Method for Reprocessing Plants
    －Instant Calculation of the Maximum Power in Criticality Accidents－
  5. 2-5 Investigation of the Sorption of Radioactive Iodine onto Rocks
    －Experimental Determination of the Sorption Distribution Coefficient－
  6. 2-6 Evaluation of Radioactivity Concentration for Site Release
    －Application of Kriging to the Evaluation of Mean Radioactivity Concentration with Consideration of Spatial Correlation－
  1. 3-1 Discrepancy in the Periodic Table Appears at Element 103
    －Successful Measurement of the First Ionization Potential of Lawrencium, Element 103－
  2. 3-2 Search for a New Type of Nuclei
    －Observation of the Bound State between Kaons and Nuclei－
  3. 3-3 Novel Magnetism in Uranium Compound Revealed by World’s Strongest Magnet
    －High-Field Magnetic Structure in URu2Si2 Observed via Nuclear Magnetic Resonance－
  4. 3-4 Switching of Electric and Magnetic Flows in Metal
    －A Possible Application of Spin Thermopower－
  5. 3-5 Surface Spin Polarization Probed by Positronium
    －Current-Induced Spin Polarization due to the Rashba Effect of the Bi/Ag Bilayer－
  6. 3-6 Digital Response Character of Cells Exposed to Ionizing Radiation
    －Single-Cell Tracking of Cell Cycle Modulation by Ionizing Irradiation－
  7. 3-7 The Newest Nuclear Data at Hand
    －Completion of a Comprehensive Portable Nuclear Decay Data Map, the “JAEA Chart of the Nuclides 2014”－
  1. 4-1 Highly Accurate Estimation of Nuclear Reactor Parameters
    －Development of a Novel Calculation Method for Calculating Reactor Kinetics Parameters with Monte Carlo Method－
  2. 4-2 Combining Two Nondestructive Elemental Analysis
    －Development of Elemental Analysis by using an Intense Pulsed Neutron Beam－
  3. 4-3 Predicting Corrosion Behavior in Nitric Acid Solution
    －Simulation of Intergranular Corrosion of Stainless Steel using the Cellular Automata Method－
  4. 4-4 Vacancies Studied by Positron Annihilation Lifetime and Hydrogen Adsorption
    －Hydrogen Embrittlement under Elastic Stress of High-Strength Steel－
  5. 4-5 Toward the Evaluation of Minor Actinide Transmutation Fuel Behavior
    －Preparation of a High-Purity Curium Sample at the Milligram Scale－
  6. 4-6 Simple, Low-Cost, Highly Efficient Treatment Technology for Radioactive Wastewater
    －Uranium Removal from Decontamination Wastewater using an “Emulsion Flow Method”－
  7. 4-7 Rapid and Reliable Analysis of Impurities in Uranium Ore
    －Mass Spectrometric Characterization of Impurities Based on Solid Sample Introduction－
  8. 4-8 Revised Database for Spent Nuclear Fuel Reprocessing
    －Handbook on Process and Chemistry of Nuclear Fuel Reprocessing, 3rd Edition－
  9. 4-9 Improved Capability for Atmospheric Dispersion Simulation
    －Enhancement of Prediction Performance of WSPEEDI-II for Middle-Range Scale Dispersion using Krypton-85 Measurement Data－
  10. 4-10 Tracking Pollutants in the Pacific Ocean
    －Drift Simulation of Tsunami Debris due to the Great East Japan Earthquake－
  11. 4-11 Development of the Particle and Heavy Ion Transport Code System, PHITS
    －Simulating the Motion of All Radiations in One Computational Code－
  1. 5-1 Instantaneous Generation and Acceleration of Fully-Stripped Fe Ions in GeV
    －Toward the Application of the Laser-Driven Heavy Ion Accelerator－
  2. 5-2 Transmission Nuclear Resonance Fluorescence Assay of a Spent Fuel Canister
    －Demonstrating Feasibility in a Realistic Scenario－
  3. 5-3 Extraction of Atomic-Level Magnetism using Synchrotron Radiation
    －Element-Specific Magnetization Measurements by Soft X-ray Magnetic Circular Dichroism－
  4. 5-4 Electron Dynamics Unveiled by Combined Use of Three Quantum Beams
    －An Inelastic Scattering Study of Spin and Charge Excitations in Superconducting Cuprates－
  5. 5-5 Elucidation of the Site-Occupancy of Hydrogen Atoms in Iron
    －In situ Neutron Diffraction under High Pressure and High Temperature－
  6. 5-6 Remarkably High Fuel Cell Performance of Graft-Type Polymer Electrolyte Membranes
    －Origin of High Proton Conductivity Revealed by Hierarchical Structure Analysis－
  7. 5-7 Observation of Residual Stresses in Structural Steel by X-ray and Neutron Diffraction
    －Contribution to the Reliability Improvement of Mechanical Components and Structures－
  8. 5-8 Understanding the Mechanism behind Gene Expression by Flexibility in DNA Structure
    －Observation of Base-Sequence-Dependent DNA Dynamics by Quasi-Elastic Neutron Scattering－
  9. 5-9 Discovery of “Aggregated DNA Lesions” by Ionizing Radiation
    －Evidence for “Clustered DNA Damage” as a Basis for Heavy Ion Beam Cancer Therapy－
  10. 5-10 Toward Reduction of Adverse Effects in Cancer Radiotherapy
    －Finding the Characteristics of the Radiation-Induced Bystander Effect－
  11. 5-11 Why Can Common Reed Grow in Salt Water?
    －Visualization of Sodium Exclusion from the Root using a Positron-Emitting Tracer Imaging System－
  12. 5-12 Two-Dimensional Neutron Measurement with High Sensitivity and High Precision
    －Development of a Novel Gas-Based Two-Dimensional Neutron Detector System－
  13. 5-13 Toward an Understanding of the Role of “Water” in the Earth’s Mantle
    －Development of a High Pressure, High Temperature Apparatus for Neutron Diffraction at J-PARC－
  14. 5-14 Neutron Diffraction Study of Phase Transformations in Steels
    －Effect of Partial Quenching on Phase Transformation in Nano-Bainite Steel－
  15. 5-15 Large-Area Uniform Ion Irradiation without Beam Scanning
    －Making the Beam Profile Uniform using Nonlinear Force－
  16. 5-16 Innovative Structural Health-Monitoring for a High Temperature Piping System
    －How to Use a Strain Gauge Processed by Femtosecond Laser Pulses－
  1. 6-1 To Achieve the First Practical Commercial High-Temperature Gas-Cooled Reactor Fuel in the World
    －Collaborative Research with the Republic of Kazakhstan Regarding the Irradiation-Performance of High-Burnup Fuel－
  2. 6-2 Solutions for Problems of Waste with the Safety, Sustainability, and Economy
    －Development of Nuclear Systems using HTGR－
  3. 6-3 Development of a Chemical Reactor Made of Industrial Structural Materials for a Hydrogen Production Process
    －Ceramic Sulfuric Acid Decomposer Resisting a Very Harsh Environment－
  4. 6-4 Toward the Establishment of Various Heat Application Systems using the HTGR
    －Investigation of Water Production Cost with Desalination using HTGR Waste Heat－
  5. 6-5 For Supplying HTGR Heat to Non-Nuclear Industry
    －Development of Safety Analysis Techniques for Cogeneration HTGR－
  1. 7-1 Demonstration of the In-Vessel Repair Technology within the Fast Reactor “JOYO”
    －Replacement of a Large Structure and Retrieval of a Deformed Test Subassembly－
  2. 7-2 Approach for Advanced Seismic Assessment Technologies for Sodium-Cooled Fast Reactors
    －Behavior of Piping for Sodium-Cooled Fast Reactors under High-Level Seismic Loads－
  3. 7-3 Visualizing the Coolant Flow in the Fuel Assembly
    －Achieving Highly Accurate PIV Measurement through Index Matching－
  4. 7-4 Physics-Based Simulation of Interfacial Dynamic Motion
    －Development of a Mechanistic Evaluation Method for Gas Entrainment Phenomena in a Fast Reactor－
  5. 7-5 Safety Study of Extraction Chromatography Technology for a Partitioning Process
    －Behavior of Heat, Hydrogen Gas, and Degradation Products in a Separation Column－
  6. 7-6 Quantification of Oxygen Behavior in Nuclear Fuel
    －Measurement of Oxygen Diffusion Coefficients in the Mixed Oxide Fuel－
  7. 7-7 Improvement of the Thermal-Hydraulic Analysis Technique for the Coolant in FBR Components
    －Evaluation of the Coolant Thermal-Hydraulics of the “MONJU” Reactor Upper Plenum using an Analytical Model－
  1. 8-1 Toward the Application of a Clearance System to the Fugen Nuclear Power Plant
    －Establishment of an Evaluation Method for Radioactive Concentration on the Contamination of a Turbine System－
  2. 8-2 Remediation of Mill Tailings Pond in a Closed Uranium Mine
    －Capping Construction using Natural Material for Long-Term Stability－
  3. 8-3 Rapid Understanding of Nuclide Composition in Radioactive Wastes
    －Development of an Analytical Method with Capillary Electrophoresis－
  4. 8-4 Development of Reasonable Confirmation Methods Concerning Radioactive Wastes
    －Study of Evaluation Methods to Determine the Radioactivity Concentrations of Radioactive Wastes Generated by Research Reactors－
  5. 8-5 Hydrochemical Disturbances in Groundwater during the Construction and Operation of the Mizunami Underground Research Laboratory
    －Variation of Groundwater Chemistry in the Last Decade－
  6. 8-6 Reduction of Groundwater Inflow in the Deep Underground
    －Countermeasures Taken during the Construction of the Mizunami Underground Research Laboratory－
  7. 8-7 Evaluation of the Mass Transport Characteristics in Rock Masses
    －Case Study Based on In situ and Laboratory Tests using Fractured Sedimentary Rock at the Horonobe URL－
  8. 8-8 Predictions of the Transmissivity of Underground Fault Zone Fractures
    －Development of a Hydrogeological Investigation Technique for Fault Zones－
  9. 8-9 Visualization at Depths between 0 and 1000 m Below Sea Level
    －Subsurface Geological Mapping of the Japanese Islands－
  10. 8-10 Performance Assessment of the Geological Disposal System in Terms of Changes in the Geological Environment
    －Radionuclide Migration Analyses Focused on the Difference between Uplift and Erosion Rates－
  11. 8-11 Mechanical Properties of Mudstone from the Wakkanai Formation
    －Strength Affected by the Degree of Saturation and Bedding Plane Orientation－
  12. 8-12 Prediction of Radionuclide Migration in a Buffer Material
    －Development of an ISD Model in Compacted Bentonites－
  13. 8-13 Determination of the Plutonium Rate Constant using a Microchannel
    －Microchip Initiates New Separation/Analytical Chemistry for Plutonium－
  1. 9-1 Development of a Fast Power-Modulation Method in Triode Gyrotron
    －Demonstration of the ITER Electron Cyclotron Heating and Current Drive System Requirement－
  2. 9-2 Achievements toward the Manufacture of the ITER Divertor
    －Development of an ITER Full-Tungsten Full-Scale Prototype Divertor－
  3. 9-3 Cable Twist Pitch Variation in Superconductors for ITER
    －Behavior of a Superconducting Cable during Cable Insertion－
  4. 9-4 Production of a Negative Ion Beam with the Largest Current in the World
    －Achievement of a 32 A Negative Ion Beam by Improvement of the Beam’s Uniformity in the JT-60SA Negative Ion Source－
  5. 9-5 Thermal Shields for a Large Superconducting Magnet
    －Establishment of a Manufacturing Method for the Thermal Shields for On-Site Assembly－
  6. 9-6 New Method for Plasma Diagnostics to Reduce Noise Effects
    －Separation of Two Signals from a Round-Trip Laser－
  7. 9-7 Study on a LOCA in a Fusion DEMO Reactor
    －Activity Toward the Establishment of Safety Design Guidelines for Conceptual Design of a Fusion DEMO Reactor－
  8. 9-8 Toward Dynamic Control of Core Plasma
    －Simulation Study on Non-Local Response in Core Plasma－
  9. 9-9 Lithium Recovery Technology for Stably Supplying Fuel to Fusion Reactors
    －World-First Dialysis Technique for Lithium Recovery from Seawater－
  10. 9-10 Modification of Plasma-Facing Material
    －Modification of Vacuum Plasma Sprayed Tungsten Coating by Friction Stir Processing－
  11. 9-11 Corrosion Inhibition using a Small Amount of Oxygen
    －Effect of Dissolved Oxygen on the Corrosion Properties of a Blanket Structural Material－
  1. 10-1 Search for the Strengthening Elements of Metals
    －Strength Prediction of Metal Materials via Quantum Mechanical Computation－
  2. 10-2 Supercomputer Simulations Solve the Puzzle of Impurity-Robust Superconductors
    －Relation between the Relativity of Electrons and Superconductivity－
  3. 10-3 Visualization of Large-Scale Data Located on a Remote Supercomputer
    －Development of a Remote Visualization System Based on Particle-Based Volume Rendering－
  4. 10-4 Analyzing Structural Soundness using “K” Computer
    －Contributing to Infrastructure Maintenance with High Earthquake Resistance through the Structural Analysis of an Assembly－
  1. 11-1 Information Infrastructure for the Identification of Illicit Nuclear and Radioactive Materials
    －Development of a Nuclear Forensics Library and Data Analysis Tool for Nuclear Forensics－
  1. 1-1 The Migration of Radioactive Iodine in Seawater
    －Variation of Iodine-129 Concentration before and after the Accident at the TEPCO’s Fukushima Daiichi NPS－
  2. 1-2 Ground Deposition Maps of Iodine-131 Obtained Using Airborne Surveys at an Early Stage of the Accident at 1F
    －A Joint Study with JAEA and DOE/NNSA－
  3. 1-3 Visualization of the Distribution of Radiocesium Concentration at the Bottom of Irrigation Ponds
    －Measurement of Irrigation Ponds Using the Plastic Scintillation Fiber－
  4. 1-4 Why Have Air Dose Rates Decreased with Time?
    －Depth Distributions of Radioactive Cesium in Soils－
  5. 1-5 Provision of Radionuclide Distribution Data
    －The Collection and Quick Provision of Environmental Monitoring Data－
  6. 1-6 Simulating the Migration Behavior of Radioactive Cesium in the Environment
    －A Case Study of the Ogaki Dam Reservoir－
  7. 1-7 Chemical Bonding between Radioactive Cesium and Clay Minerals Revealed by Supercomputer
    －First-Principles Calculation Studies of the Chemical Adsorption Form of Cesium on Clay Minerals－
  8. 1-8 Translocation of Radioactive Fallout Cesium in Trees
    －Analysis of the Distribution of Radioactive Cesium in Plants Using Autoradiography－
  9. 1-9 Easy Monitoring of the Radioactive Cesium Concentration in Water
    －A New Assay System Using a Cesium Adsorption Disk and the GM Survey Meter－
  10. 1-10 Assessment of Radiation Dose Reduction of Radioactive Cesium in Buildings
    －Numerical Simulation Analysis Using Building Models－
  11. 1-11 Detection of Defects in the Fuel Cladding Tube
    －Development of a Defect Detection Technique Using High-Resolution X-ray Computed Tomography－
  12. 1-12 Laser Spectroscopic Analysis of Underwater Debris in a Nuclear Reactor Core
    －A Contribution to the Decommissioning of the TEPCO’s Fukushima Daiichi NPS－
  13. 1-13 Melting and Crushing of Fuel Debris with Laser Light as a Heat Source
    －Countermeasures to Fuel Debris Characterized by Indefinite Shapes, Higher Hardness, Multi-Ingredients, and Porous Bodies－
  14. 1-14 Maintaining the Integrity of the Reactor Vessel until the Completion of Fuel Removal
    －The Influence of Radiation on the Corrosion of Vessel Steels and Corrosion Measures－
  15. 1-15 Estimation of the Chemical Form of Fuel Debris in a Reactor Pressure Vessel
    －Estimation with the Help of Thermodynamic Calculation－
  16. 1-16 What Has Formed from the Melted Fuel and Control Blade?
    －Investigating the Characteristics of Solidified Core Melt－
  17. 1-17 Management of Removed Fuel Debris
    －A Study of Treatment Scenarios for Fuel Debris after Removal－
  18. 1-18 An Exploration of the Reason for Iodine-131 Release after Core Cool Down
    －Release of Iodine-131 from Contaminated Water in the Basement of Reactor Buildings－
  19. 1-19 Safe Storage of Spent Cesium Adsorbent
    －Characterization and Evaluation for Hydrogen Production and Corrosion－
  20. 1-20 Development of an Analysis Method for a Hard-To-Measure Nuclide in Wastewater
    －Cadmium-113m Analysis Method Using β-ray Measurement－
  21. 1-21 Toward the Treatment and Subsequent Disposal of the Accident Waste
    －An Analysis of Rubble and Trees Collected from the Site of the TEPCO’s Fukushima Daiichi NPS－
  1. 2-1 Fuel Failure Processes Revealed by Numerical Approach
    －Simulation of Fracture Behavior Using Damage Mechanics Model－
  2. 2-2 Improving Structural Integrity Assessment of Reactor Pressure Vessels
    －Effect of Neutron Irradiation on Fracture Properties of Stainless Overlay Cladding for Reactor Pressure Vessel－
  3. 2-3 Structural Integrity Assessment of Nuclear Components Operated over a Long Period
    －Probabilistic Fracture Mechanics Analysis for Ni-Based Alloy Welds－
  4. 2-4 Investigating Gas Inflow Influences in Accidents
    －Concentration Analysis with Gas Measurement Device－
  5. 2-5 Dissolution of Compacted Clays in High-Level Radioactive Waste Repositories
    －Alkaline Dissolution Inhibited by Accessory Minerals in Bentonite－
  6. 2-6 Acquisition of Evaluation Data for Severe Accident in Reprocessing Plant
    －Acquisition and Evaluation of Airborne-Release Data from Boiling Accident－
  1. 3-1 Flow of Spins Resulting from Acoustic Wave
    －Towards Rare-Metal-Free Magnetic Devices－
  2. 3-2 Elucidation of the Spin State of Conduction Electrons in Graphene
    －Significant Progress for Spintronic Applications of Two Dimensional Materials－
  3. 3-3 A Precursor to Exotic Superconductivity
    －Nematicity and Superconductivity in URu2Si2－
  4. 3-4 Hydrogen-Induced Insulation Degradation of Ceramic Capacitors
    －Microscopic Evidence Provided by Muons－
  5. 3-5 A Study to Reveal the Mechanism of Radiobiological Effects
    －DNA Damage Induces Aberrations in Normal Chromosomes in a Living Cell－
  6. 3-6 Discovery of Uranium Migration in Groundwater with Silica Colloid
    －Devisal of an Effective Method for Elucidating the Chemical Forms of Trace Actinides in Environmental Water－
  7. 3-7 Search for 6ΛH Hypernuclei
    －Can We Make Neutron-Rich Hypernuclei?－
  1. 4-1 Improving the Prediction Accuracy of the Decay Heat from Nuclear Force
    －Clarify Effect of Tensor Force on β Decay－
  2. 4-2 Understanding the Behavior of Molten Material in Severe Accidents
    －Developing Numerical Simulation Method of Melt Relocation－
  3. 4-3 Improving Uranium Accountancy
    －Demonstration of a Novel Nondestructive Assay for Nuclear Waste Drums at Ningyo-toge－
  4. 4-4 Improving the Evaluation Accuracy of the Long-Term Integrity of Nuclear Reactors
    －Developing a Model of the Microstructural Evolution under Neutron Irradiation－
  5. 4-5 Developing a Database of Fundamental Properties for Partitioning and Transmutation
    －Evaluating Thermodynamic Data on Intermetallic Compounds with Electrochemical Techniques－
  6. 4-6 Extraction of Strontium Using a Macrocyclic Compound
    －Extraction Enhanced by Applying Ionic Liquid Solvents－
  7. 4-7 Controlling Valences by Electrocatalysis of Pt Particles
    －Rapid and Selective Valence-Control Method for Actinide－
  8. 4-8 Selective Detection of Higher Enriched Uranium Particles
    －Secondary Ion Mass Spectrometry Combined with Solid-State Nuclear-Track Detection－
  9. 4-9 Mechanism of Greenhouse Gas Emission from Rice Paddy
    －Simulation of Atmospheric Ammonia Exchange Using the Land Surface Model for Transport of Radioactive Materials－
  10. 4-10 Influence of Physical Characteristics on Internal Dosimetry
    －Use of Human Models to Compare Caucasians with Japanese －
  11. 4-11 Ensuring the Reliability of Measurements of Exposure of Workers and Public to High-Energy γ-rays
    －Establishment of the High Energy γ-ray Calibration Field－
  12. 4-12 Measuring Radiation Intensity in Nuclear Reactors
    －Developing γ-ray Detectors for Remote Inspection in Primary Containment Vessel－
  13. 4-13 Technical Development for In-Pile Irradiation-Assisted Stress Corrosion Cracking Test Capsules
    －Research on Safety Evaluation of Light Water Reactors－
  14. 4-14 Developing a Real-Time Management System for Workers in Radiation-Controlled Areas
    －Worker-Safety Management in Radiation Controlled Areas－
  1. 5-1 Biocompatible Plastic Fabrication by Ion Beam
    －Development of Micro/nanofabrication and Surface Modification Technique Using Focused Ion Beam for Medical Applications－
  2. 5-2 Application of Composite-Type Optical Fiber Technique for Medical Instrument Development
    －Industrialization of Composite-Type Optical Fiber Technique and Startup of JAEA-Supported Venture Business－
  3. 5-3 Doping Effect of Ferroelectrics
    －Improvement of Ferromagnetic Mechanism of Bismuth Ferrite－
  4. 5-4 Distinction between Polarizations Induced by Magnetic Cycloids and Exchange Striction
    －Importance of Magnetic Cycloids for Multiferroic Materials－
  5. 5-5 Development of an Aluminum-Based Hydrogen Storage Alloy
    －To Realize Light-Weight Hydrogen Storage Alloys－
  6. 5-6 Synchrotron Radiation Mössbauer Absorption Spectroscopy Improved by Electron Detection
    －Highly Efficient Mössbauer Spectroscopy of Many Periodic Table Elements Is Now Achievable－
  7. 5-7 Toward the Development of Protein Absorbents for Rare and Harmful Metals
    －Structural Characteristics of Halophilic Proteins Clarified by a Quantum Beam－
  8. 5-8 Observation of Living Cells under a Soft X-ray Microscope
    －Laser Plasma Soft X-ray Microscope with a Combination of Intense Laser Plasma Soft X-ray Source and Contact Microscopy－
  9. 5-9 Inhibition of Cadmium Movement in Crops by a Peptide
    －Visualization of Elements in Roots Using a Positron-Emitting Tracer Imaging System－
  10. 5-10 Challenge for Nanoscale Analysis by X-ray Spectroscopy in Combination with Electron Microscopy
    －Development of a Multilayer Grating Spectrometer for Use with Electron Microscopes－
  11. 5-11 Discovery of X-ray Coherent Mirage
    －Indication of the Potential of New X-ray Optics Using Plasma－
  12. 5-12 Transparency of Sodium in the Ultra-Violet Spectral Range
    －Imaging by Light Illumination through an 8-mm-Thick Sodium Sample－
  13. 5-13 Innovative Technique for Elucidating Diffusion through Materials
    －Development of an Advanced Analysis Method for Quasielastic Neutron Scattering－
  14. 5-14 Achievement of High-Quality Pulsed Cold Neutron Beam
    －Performance Evaluation of the J-PARC Cryogenic Hydrogen System－
  15. 5-15 Dose Rate after Beam Operation of J-PARC 3 GeV Synchrotron
    －Investigation and Measurement of Dose Rate Distribution of Radioactive Nuclides Produced in the Accelerator for Higher Output Power－
  16. 5-16 Magnetic Shielding via Vacuum Chambers for Beam Orbit Stabilization
    －Development of Vacuum Chambers of Magnetic Materials at J-PARC－
  17. 5-17 Observation of the Beam Injected into the Acceleration Region of the Cyclotron
    －Development of an Emittance and Acceptance Measurement System－
  1. 6-1 Demonstration Plan for the World’s First Nuclear Heat Application with the High Temperature Engineering Test Reactor
    －Toward the Industrial Use of Nuclear Heat－
  2. 6-2 Compatibility between Effective Plutonium Incineration and Nuclear Proliferation Resistance
    －Conceptual Study of a Plutonium Burner High Temperature Gas-Cooled Reactor System－
  3. 6-3 Economic Evaluation of a High Temperature Gas-Cooled Reactor Iodine-Sulfur Process Hydrogen Production System
    －Investigation of Hydrogen Production Cost and Competitiveness－
  4. 6-4 Toward a Demonstration that Reactor Safety Can Be Secured Using Only Natural Phenomena
    －To Establish a Test Procedure to be Employed Soon after Restart－
  1. 7-1 Investigation of Molten Core Material Behavior
    －An Experimental Study on the Containment of Core Disruptive Accidents－
  2. 7-2 Aiming for Robustness for the Reactor Building to Withstand Severe Natural Disasters
    －Evaluation of External Hazards to the Reactor Building－
  3. 7-3 Numerical Simulation for Safety Evaluation of the Steam Generators in Fast Reactors
    －A Multiphysics Evaluation System for Tube Failure Accidents－
  4. 7-4 Challenges Facing the Improvement of Inspection Technology for Steam Generator Tubes
    －Large Scale 3D Simulations of ISI of FBR “Monju” SG Tubes Using ECT－
  5. 7-5 Development of Long Life Fuel Cladding Tube for the Fast Reactor
    －11Cr-ODS Steel with Sufficient Strength, Toughness, and Corrosion Resistance－
  6. 7-6 Toward a New Reprocessing Process for the Transitional Period to the Fast Reactor Cycle
    －The Development of a Uranium and Plutonium Co-recovery Process (Co-processing Process)－
  1. 8-1 Toward an Optimized Decommissioning Plan
    －Development of Formula to Evaluate Manpower Requirements for Dismantling Nuclear Facility－
  2. 8-2 Efficient Separation of Uranium from Sludge-Like Uranium-Bearing Waste
    －Developing Process to Selectively Separate Uranium by Using Hydrochloric Acid－
  3. 8-3 Developing Rapid Method to Analyze Radioactive Waste
    －Developing Method to Analyze 242mAm in Low-Level Radioactive Waste－
  4. 8-4 Study to Improve the Safety of Trench Facility
    －Suppression of Infiltrated Water to Reduce Radioactive Substances from the Facility－
  5. 8-5 Visualization of Geosynthesis Procedure
    －Geosynthesis Data Flow Diagram (Construction Phase)－
  6. 8-6 Research in Onshore Mud Volcanism
    －Origin of Muddy Sand from Kamihoronobe Mud Volcano－
  7. 8-7 Investigation of Damage to Rock Mass in Gallery Excavation
    －Based on Seismic Velocity and Fracture Distribution around Gallery Wall－
  8. 8-8 Detection of Unrecognized Volcanic Activity by Sand Grain
    －Developing Method based on Mineral and Chemical Analysis of Sand Grain in Sedimentary Rock－
  9. 8-9 Large Inland Earthquake Triggered by Latent Magmatism
    －Helium Isotopes as a Tool for Detecting Concealed Active Faults－
  10. 8-10 Prediction of Radionuclide Speciation in Groundwater
    －Determination of Standard Thermodynamic Data of Se(VI)/(IV) Couple－
  11. 8-11 Prediction of Long-Term Alteration Characteristics of HFSC
    －Clarification of Decreasing pH and Development of Alteration Model－
  12. 8-12 Evaluation of Long-Term Geological Evolution
    －Study of the Safety of Geological Disposal Considering Uplift and Erosion－
  13. 8-13 Improvement of Ruthenium Removal Rate by Electrochemical Oxidation
    －Improvement of Stable Operation for Vitrification Process－
  1. 9-1 Lifetime Extension of Beam Dump by Dispersing the Deposition of Laser Energy
    －A High Laser Energy-Resistant Beam Dump for Thomson Scattering in ITER－
  2. 9-2 Investigation of Strain Using Neutron Diffraction
    －A Foundation for Improvement of ITER Conductor Performance－
  3. 9-3 Failure Behavior of the Hot Isostatic Pressed Joint in the Fusion Blanket
    －The Latest Highlight of Research and Development of Reduced Activation Ferritic/Martensitic Steel for Use in the Fusion DEMO Reactor－
  4. 9-4 Toward the Construction of an Intense Neutron Source that Produces Fusion Reactor Conditions
    －Engineering Validation Research and Engineering Design of the Lithium Facility－
  5. 9-5 Disassembly of the Japan Torus-60 Tokamak Device for the Japan Torus-60 Super Advanced Project
    －Disassembly of Large Radioactivated Structures－
  6. 9-6 Accurate Winding of a Nb3Sn Superconducting Magnet
    －Development of JT-60SA Central Solenoid for Precise Plasma Control－
  7. 9-7 World Record-Setting Dual-frequency Gyrotron
    －The Development for Electron Cyclotron Resonance Heating in JT-60SA－
  8. 9-8 Improvement of the Stability Analysis Model for Rotating Plasmas
    －Introducing Rotation Effects into the Kinetic-Magnetohydrodynamic Model－
  9. 9-9 Safe Shutdown Scenarios for Fusion Reactors
    －The Development of a High-Energy Runaway Electron Simulation Code－
  10. 9-10 Removing Fuel from the Nuclear Fusion Blanket
    －Investigation of Tritium Recovery from a Future Fusion Blanket－
  11. 9-11 Stably Supplying Fuel Tritium to Fusion Reactors
    －Establishment of a New Pebble Fabrication Technology for an Advanced Tritium Breeder－
  1. 10-1 Helium Induces Grain Boundary Fracture of Iron
    －Finding a Universal Law of Grain Boundary Strength Loss Using a Supercomputer－
  2. 10-2 Toward Reliability Enhancement of Seismic Risk Assessment of NPP
    －Proposal for a Ground Motion Generation Method that Combines a Fault Model and Frequency Prediction－
  3. 10-3 Simulations for Superconductors with High-Performance Eigenvalue Solver
    －Toward Real-Size Scale Simulations－
  4. 10-4 Massively Parallel Techniques for Realizing 105 Times Higher Spatio-Temporal Resolutions
    －The K Computer Sheds Light on Multi-Scale Turbulence in Fusion Plasma－
  1. 11-1 A Probabilistic Expression for Physical Protection Performance in a Nuclear Facility
    －A Quantification Method for Physical Protection Performance－
  1. 1-1 Time Series Observations in the Coastal Regions off Northern Ibaraki
    -Factors Controlling Concentrations of Radiocesium in Seabed Sediment-
  2. 1-2 Creating Dose Rate Maps over Wide Areas in Collaboration with Municipalities
    -Detailed Measurements of Air Dose Rates Using Car-Borne Survey-
  3. 1-3 Measurement Method without Exposure to Radiation Dose
    -Radiation Measurement of Area Surrounding 1F using Unmanned Helicopter-
  4. 1-4 Surface Grinding of Gravel for Waste Reduction and Reuse
    -Decontamination Test of Gravel by General-Purpose Machine-
  5. 1-5 Supercomputer Solves Mystery of Strong Affinity of Soil to Radioactive Cesium
    -First-Principles Calculation Reveals Mechanism of Cesium Adsorption to Soil-
  6. 1-6 Specific Sorption of Radiocesium by Minerals
    -Toward Remediation of Soils Contaminated by Radiocesium-
  7. 1-7 Transport of Radionuclides in Depth Direction
    -Investigation on Depth Distribution of Radionuclides in the Soil of Fukushima-
  8. 1-8 Retention of Mobile Radiocesium in Forest Surface Soils
    -Quantifying Microbial Uptake and Abiotic Adsorption-
  9. 1-9 Water Purifier for Securing Water
    -Development of Grafted Adsorbent for Cs Removal-
  10. 1-10 Assessment of Doses to Inhabitants Living in Fukushima Prefecture
    -Approach to Assessing the Doses Considering Areal Differences in Contamination and Interpopulational Differences in Lifestyle Habits-
  11. 1-11 For the Safe Handling of Dehydrated Sludge Contaminated by Radioactive Cesium
    -Dose Estimate for Workers and Public with Incineration and Disposal of Dehydrated Sludge-
  12. 1-12 Inhibiting Corrosion of Metallic Materials in Spent Fuel Pools
    -Verification of Removal Effect of Dissolved Oxygen Using Hydrazine-
  13. 1-13 Characterization of Fuel Debris in Severe Accident
    -Properties of Fuel Debris for Developing Defueling Operations-
  14. 1-14 What Has Formed on the Fuel Debris Surface by Sea Water Injection?
    -High-Temperature Reaction Products between Simulated Fuel Debris and Salt Deposits-
  15. 1-15 Prevention of Re-Criticality in Fuel Debris in the Damaged Cores
    -Criticality Characteristics of Fuel Debris Containing Concrete-
  16. 1-16 Nuclear Material Accountancy for Molten Core Material by γ-ray Measurement
    -Development of Nuclear Material Measurement Technology using Passive γ Spectrometry of Molten Core Material-
  17. 1-17 Calculation of Decay Heat Causing Core Meltdown
    -Three-Dimensional Decay Heat Analysis for the TEPCO’s Fukushima Daiichi NPS-
  18. 1-18 What’s the Point of Analyzing the Fukushima Accident?
    -Review of Five Investigation Reports on Fukushima Accident-
  19. 1-19 Mechanism of Cesium Absorption on Zeolite
    -First-Principles Study of Structural Effects on Absorption in Zeolites-
  20. 1-20 Decontamination of Radioactive Cobalt and Manganese with Radioactive Cesium
    -Simplified Treatment Process of Radioactive Liquid Waste by Adding Hexacyanoferrate(II) Ions-
  21. 1-21 Comprehension of Radioactive Contamination inside the Reactor Buildings
    -Radioanalysis of Concrete Core Boring Samples-
  1. 2-1 Robustness of JSFR against Earthquakes and Tsunamis
    -Effectiveness of Natural Convection in a Decay Heat Removal System-
  2. 2-2 Measurement of Temporospatially Fluctuating Flow
    -Development of Ultrasonic Flowmeter for Fast Reactor-
  3. 2-3 Aiming at Improved Visualization Technology for Reactor Structures
    -Experiment on Sodium Wetting on USV Sensor Surface-
  4. 2-4 Codification of Materials for Demonstration Fast Reactor in JSME Code
    -Establishment of Standards for Material Strength and Elevated Temperature Design for 316FR and Modified 9Cr-1Mo Steels-
  5. 2-5 Investigation of Sodium/Water Reaction in Collaboration with France
    -Sodium/Water Reaction Test for Steam Generator Heat Transfer Tube-
  6. 2-6 Controlling Oxygen Content of U-Pu Mixed Oxide Fuel
    -Oxygen Potential Measurement and Application to Fuel Technologies-
  1. 3-1 Spatial Distribution of Fractures in Granite
    -Influence of the Initial Cooling of the Granitic Pluton-
  2. 3-2 Advancing In Situ Rock Stress Measurement Techniques at the Mizunami Underground Research Laboratory
    -Case Study: Successful Overcoring Tests Excluding Groundwater-
  3. 3-3 Long-Term Investigation of an Excavation Damaged Zone around a Gallery
    -Seismic Tomography Survey for Investigation of an EDZ-
  4. 3-4 Regional Estimate of Fracture Permeability
    -Hydrogeological Investigation of Sedimentary Rocks-
  5. 3-5 Dating Fault Activity
    -K-Ar Age of Fault Clay-
  6. 3-6 Estimating Long-Term Evolution of Environment and Materials around Radwaste in Deep Underground
    -Development of Assessment Methodology Considering Geochemical Changes in the Near-Field-
  7. 3-7 Effect of Natural Organic Matter on Migration of Radionuclides
    -Metal Ion Binding Abilities of Deep Groundwater Humic Substances-
  8. 3-8 Evaluation of Bentonite Alteration in a TRU Waste Geological Repository
    -Modeling of Smectite Dissolution Rate under a Range of Chemical Conditions-
  1. 4-1 Multi-Parameter Measurement Using Laser Polarimetry for Fusion Reactor
    -Simultaneous Measurement of Magnetic Field, Electron Density, and Electron Temperature-
  2. 4-2 Manufacturing of ITER Divertor Prototype
    -First Step toward Manufacturing of Actual ITER Divertor-
  3. 4-3 Success in Beryllide Pebble Fabrication
    -Development of Granulation Technology for Neutron Multiplier Needed for Production of Fusion Reactor Fuel-
  4. 4-4 Accuracy Validation of Nuclear Data for Fusion Reactor Design
    -Toward More Accurate Fusion Reactor Design-
  5. 4-5 Toward Construction of Intense Neutron Source for Fusion Reactor Conditions
    -Measurement of Thickness and Stability of High-Speed Lithium Flow-
  6. 4-6 Realization of Fusion Intense Neutron Source
    -Loop Antenna Development for RF Coupling in the RFQ Linac-
  7. 4-7 Progress in Satellite Tokamak Program Project
    -Start of Assembly of JT-60SA-
  8. 4-8 Progress in Predicting the Voltage Holding Capability for Large Negative Ion Source
    -Key Factor for High-Energy Accelerator toward JT-60SA and ITER-
  9. 4-9 Realization of Compact Joint for Superconducting Coil
    -Development of Butt Joint Technique for Central Solenoid of Fusion Device-
  10. 4-10 Clarification of Hydrogen Isotope Dependence of Plasma Heat Diffusion
    -Contribution to the Prediction of Fusion Power in ITER-
  11. 4-11 Fast Ion Transport Study Using HELIOS
    -Fast Ion’s Dance with Alfvén Waves in ITER Plasma-
  1. 5-1 Enhancement of Thermal Stability of Nanocomposites
    -The Role of Nano-Additives on Order-Disorder Transition of Nanocomposites-
  2. 5-2 Quantitative Analysis of Conformational Changes in Proteins upon DNA Binding
    -Toward an Understanding of the Molecular Mechanisms of Protein-DNA Recognition-
  3. 5-3 Clear Imaging of Tumor with D-Amino Acid
    -Development of a Novel Amino Acid Tracer, D-[18F]FAMT, for PET Diagnosis of Cancer-
  4. 5-4 Use of Diamonds for Single Ion Detection
    -Real-Time Detection of Ion Impact Position by Fluorescence of Nitrogen Vacancy Centers-
  5. 5-5 Toward Nondestructive Assay of Fissile Materials
    -Generation of 500 keV Electron Beam from DC Photoemission Gun-
  6. 5-6 Relativistic Harmonics from Tenuous Plasma
    -Discovery of a New Compact Coherent X-ray Source-
  7. 5-7 Heatproof Seismic Sensors Guard Aging Nuclear Power Plants
    -Application of Femtosecond Laser Processing to Maintenance Study-
  8. 5-8 How Does a Cocatalyst Enhance the Activity of the Oxygen Reduction Reaction?
    -Improvement of Fuel Cell Performance-
  9. 5-9 Self-Assembled Structure of Coordination Species Clarified by Quantum Beam Techniques
    -Development of Reprocessing Techniques by Elucidation of Solution States-
  10. 5-10 Elucidation of Electronic Excitation in Novel High-Tc Superconductor
    -Resonant Inelastic X-ray Scattering Study of Iron-Pnictide Superconductor-
  1. 6-1 Evaluating the Amount of Fission Gas in Fuel with Higher Accuracy
    -Development of a Rate-Law Model of Fission Gas Bubble Growth-
  2. 6-2 Predicting Crack Growth in Reactor Piping under Large Seismic Loading
    -Proposed Method of Evaluating Crack Growth under Random Cyclic Loading-
  3. 6-3 Measuring Amount of Nuclides in Spent Nuclear Fuel
    -Development of Method of Assaying Barely Measurable Elements in Spent Nuclear Fuel-
  4. 6-4 Research on Thermal Aging Embrittlement of Cast Stainless Steels
    -Study of Thermal Aging Embrittlement in “FUGEN” Nuclear Reactor-
  1. 7-1 Electricity Generation by Nanomagnet Dynamics
    -Magnetic Power Inverter Based on Spinmotive Force-
  2. 7-2 Toward Experimental Determination of the First Ionization Potential of the Heaviest Actinide
    -New Ionization Potential Measurement Using Surface Ionization Process-
  3. 7-3 Manipulation of Electrons by Pressure
    -Coupling between Lattice and Electrons in Superconductor URu2Si2-
  4. 7-4 Novel Mechanism of Radiation Damage to DNA
    -An Advance in Elucidating the Radiation Process in DNA Damage-
  5. 7-5 Evaluation of Electron Spin Using Its Antiparticle
    -Development of a Positron Beam with the World’s Highest Spin Polarization-
  1. 8-1 Method of Accurately Designing New Types of Reactors
    -Advanced Method Using Experiments (Extended Cross Section Adjustment)-
  2. 8-2 Accurate Prediction of Nuclear Fragmentation by Energetic Radiation
    -Fragmentation Cross Section Measurement by New Method and Theoretical Model Development-
  3. 8-3 Life Prediction of Material in Nuclear Reprocessing Plants
    -Corrosion Characteristics of Stainless Steel in Boiling Nitric Acid Solution Including Np-
  4. 8-4 Discovery of Thermochromic Uranium Complexes
    -Coordination Chemistry in Ionic Liquids Using Time-Resolved Laser-Induced Fluorescence Spectroscopy-
  5. 8-5 Attempt to Establish a Reprocessing System That Uses Monoamides
    -Continuous Extraction of Uranium and Plutonium Using Mixer-Settler Extractors-
  6. 8-6 One-Pot Biofabrication of Protein-Decorated Gold Nanoparticles
    -Facile, Rapid, and Efficient Biofabrication and Immunoassay-
  7. 8-7 Analysis of Age Determination of Individual Plutonium Particles
    -Contribution of Development of Ultra-Trace Analytical Technique to IAEA Safeguard Activity-
  8. 8-8 Detailed Simulation of Transfer of Radioactivity in Land Surface Ecosystems
    -Development of Nuclide Transport Model for Atmosphere-Vegetation-Soil System-
  9. 8-9 Subsurface Soils Participate in Global Carbon Cycle
    -Carbon Dynamics Revealed by Tracing “Bomb” Radiocarbon over Past Half-Century-
  1. 9-1 Small Nuclear Reactor for Multiple Heat Applications with Attractive Safety Features
    -Conceptual Design of Small High-Temperature Gas Cooled Reactor for Developing Countries-
  2. 9-2 Proposal for HTGR Safety Design Criteria upon User Request
    -Allow H2 Plant Construction Coupled to HTGR under Non-Nuclear Regulations-
  3. 9-3 Increased Energy Efficiency for Hydrogen Production
    -Study of Ion Permeation Mechanism in Membrane of HI Concentrator-
  1. 10-1 Successful Development of Nitrate Decomposition Technology
    -For Safe Disposal of Low-Level Radioactive Waste-
  2. 10-2 Simplification of Analysis of Actinides in Radioactive Wastes
    -Development of an Analytical Method using Capillary Electrophoresis-
  1. 11-1 Moving Hydrogen Enhances Cracking in Iron
    -Embrittling Effect of Mobile Hydrogen Clarified by First Principles Calculations-
  2. 11-2 Properties of New Materials with Topology
    -Classification of the Properties in Superconductors by Topology-
  3. 11-3 Massively Parallel Fusion Plasma Simulation using 105 Processors
    -Development of Latency-Hiding Communication Technique-
  4. 11-4 Technology to Speed up Fluid Structure Interaction Simulation
    -Simulation Technologies for Flow-Induced Vibration in a Nuclear Power Plant-
  1. 13-1 Challenge of Industrial Application of Repair Technologies for FBR Heat Exchanger Tubes
    -Success in High-Accuracy Wire Feeding to Laser-Irradiated Spot-
  2. 13-2 Radiocesium in the Environment
    -Radiation Situation in Tokai Two Years after the 1F Accident-
  3. 13-3 Neutrons in Development of High-Performance Materials
    -Role of Deformation-Induced Transformation in TRIP Steels Revealed by Neutrons at J-PARC-
  4. 13-4 Development of Ultraprecise Focusing Supermirrors with Elliptical Surface
    -Focusing Gain of 52 Achieved for Advanced Instrumentation at J-PARC-
  5. 13-5 Beam Acceleration by Axially Symmetric Field
    -Development of J-PARC Annular-Ring Coupled Structure-
  6. 13-6 Development of Domestic 99Mo Production by (n, γ) Method
    -Fabrication Technology for High-Density MoO3 Pellet-
  7. 13-7 Corrosion Behavior of Metals in Sodium
    -Compatibility of Zirconium Alloy with High-Temperature Sodium-
  8. 13-8 Reliable Management of Instrumentation to Ensure Reactor Safety
    -Establishment of Damage Detection Method for Neutron Detector in High-Temperature Gas-Cooled Reactor-
  9. 13-9 Microfabrication of Teflon with Ion Microbeams
    -Development of New Microfabrication Techniques for Polymer Surfaces-
  10. 13-10 Excavation of Galleries at -500 m Depth
    -Construction of Shafts and Research Galleries for the Mizunami Underground Research Laboratory-
  11. 13-11 Investigation of Properties of Radon Hot Springs
    -Radon-Induced Biological Responses and Its Biokinetics-
  1. 1-1 Radionuclides Discharged into the Atmosphere
    -Source Term Estimation and Atmospheric Dispersion Simulation Using WSPEEDI-
  2. 1-2 Radionuclides Released into the Ocean
    -Diffusion Simulations for Regions Adjacent to Japan-
  3. 1-3 Collection and Provision of Environmental Radioactivity Data
    -Publication of Data for Environmental Reconstruction-
  4. 1-4 How Far Did Radionuclides Diffuse from the Accident?
    -Measurement of Atmospheric Anthropogenic Radionuclides Using the CTBT IMS Network-
  5. 1-5 Detailed Investigation of Radionuclide Distributions in the Environment
    -Construction of Soil Deposition Map and Dose Rate Map-
  6. 1-6 Radiation Dose Map of Japan Using an Aircraft
    -Visually Grasping the Influence of the Accident-
  7. 1-7 Effects of Forest Decontamination on the Reduction in External Exposure Doses
    -Field Demonstration of Forest Decontamination-
  8. 1-8 Creating Decontamination Guidelines Based on Practical Actions
    -Decontamination Pilot Project-
  9. 1-9 Cleanup of Cesium-Contaminated Soil
    -Investigation of Removal of Radiocesium from Soil by In Situ Ground Heating-
  10. 1-10 Decontamination of Soil Using a Poly-Ion Complex and Clay
    -Decontamination of Soils Polluted by Radioactive Cesium and Prevention of Recontamination-
  11. 1-11 Decontamination of Playground Lot
    -Trial Decontamination and Its Effects on Air Radiation Dose Rate-
  12. 1-12 Tool for Planning Rational and Effective Decontamination
    -Development of Computer Software for Efficiently Predicting Dose Rates after Decontamination-
  13. 1-13 A Simple Method for Selective Measurement of Cesium 134 and 137
    -Utilization of Common NaI(Tl) Scintillation Spectrometers-
  14. 1-14 Fibrous Grafted Adsorbents Help in Cleanup of Contaminated Water
    -Development of Fibrous Adsorbent for Removal of Radioactive Cesium-
  15. 1-15 Development of a Highly Cesium-Selective Adsorbent for Volume Reduction
    -Molecular Design of Crown Ether Using New Chemical Bond Property-
  16. 1-16 Verification of the Exposure Reduction Effect of Tap Water Restrictions
    -Evaluation of Averted Doses to Infants in the Implementation after the Accidents at the TEPCO's Fukushima Daiichi NPS-
  17. 1-17 Visualization of Distribution of Fallout Radioactive Cs in Plants
    -Toward Unveiling the Present Status of Forest Contamination-
  18. 1-18 Data Acquisition for Analysis of the Melt Progress in the Reactor Core
    -Thermal Properties of Molten Fuel from Three Mile Island Unit 2-
  19. 1-19 Prediction of the Core Meltdown of the TEPCO's Fukushima Daiichi NPS Unit 1 Reactor
    -Evaluation of the Influence of an Isolation Condenser on Core Cooling Using the TRAC Code-
  20. 1-20 How to Avoid Core Damage in Unit 2 of the TEPCO's Fukushima Daiichi NPS
    -Evaluation of the Efficiency of Alternative Water Injection Timing through Accident Analysis-
  21. 1-21 Toward Safe Management of Accident Waste
    -Challenges to Long-Term Storage, Processing, and Disposal of Waste-
  22. 1-22 Decontamination of Radioactive Strontium to Make Fresh Water
    -Application of a Strontium Adsorbent Prepared for Use with Radioactive Waste Solutions from Nuclear Fuel Reprocessing-
  23. 1-23 Evaluation of Hydrogen Production from Waste Zeolite Adsorbents
    -γ-Radiolysis of Mixtures of Zeolites and Seawater-
  24. 1-24 Development of Special Measuring Equipment Using JMTR Irradiation Techniques
    -A New Water-Level Indicator Applicable under Severe Conditions-
  1. 2-1 Japanese Fast Reactor Technologies Draw the Attention of Electricité de France
    -Safety Improvement and Mass-Volume Reduction of the JSFR-
  2. 2-2 Containment of Core Disruptive Accidents
    -Fuel Discharge Behavior in a Fuel Assembly with Inner Duct Structure-
  3. 2-3 Prediction of the Flow Structure in Large Diameter Elbows
    -Evaluation of Flow-Induced Vibration in Large Diameter Pipes in the JSFR-
  4. 2-4 For Enhancement of the Reliability of SFR Pipe Designs
    -Creep Strength Assessment of Mod.9Cr-1Mo Steel Welds Taking Type-IV Damage into Account-
  5. 2-5 The "MONJU" Core Can Be Cooled during a Station Black-Out
    -Core Cooling Capability during an Earthquake and Subsequent Tsunami-
  6. 2-6 Toward Highly Efficient Production of MOX Fuel
    -Confirmed Feasibility of Production from Agitated Granular Powder-
  1. 3-1 Study of the Groundwater Flow in Coastal Areas
    -Optical Measurement of the Salinity Distribution on the Saltwater Wedge-
  2. 3-2 Understanding the Impact of Nitrates on Geological Disposal Systems
    -Modeling of the Chemical Transition of Nitrates Accompanied by Corrosion of Carbon Steel-
  3. 3-3 Challenges of Seepage Control at a Repository for Radioactive Waste
    -Applicability of a Grout Penetration Model-
  4. 3-4 Looking at Huge Earthquakes through a 0.1 mm Grain
    -Thermochronology with a Single Grain Using the (U-Th)/He Method-
  5. 3-5 Fault Zone Determination through Multivariate Analysis
    -Case Study Using a Dataset from a Deep Borehole-
  6. 3-6 Technology for Estimating Hydrogeological Characteristics Deep Underground
    -Evaluation of Hydrogeological Characteristics Using Water Pressure Data-
  7. 3-7 Development of a Methodology for Reconstructing Very Long-Term Geosphere Evolution
    -A Very Long-Term Groundwater Flow Analysis Using Numerical Simulation-
  8. 3-8 Examination of the EDZ Developed around a Tunnel
    -Estimation of the EDZ by Seismic Tomography Investigation-
  9. 3-9 Evaluation of the Initial Stress Distribution Deep Underground
    -Three-Dimensional Initial Stress Measurement by Hydraulic Fracturing-
  1. 4-1 Manufacture of Superconductors for ITER Coils
    -Progress in Procurement of Superconductors for TF Coils, with Japan Leading in the World-
  2. 4-2 A Laser System for Plasma Diagnostics Has Achieved the World's Best Performance
    -Development of YAG Laser for the Edge Thomson Scattering System in ITER-
  3. 4-3 Attainment of Large-Scale 3D Multibeam Analysis
    -Compensation for Beam Deflections in the Accelerator of ITER NBI-
  4. 4-4 Overview of IFERC Project
    -Activities of DEMO Design and R&D Coordination Centre, and Computational Simulation Centre-
  5. 4-5 Achieving Safety in the Deuteron Accelerator Facility
    -Development of a Safety Protection System for the IFMIF/EVEDA Accelerator-
  6. 4-6 Progress in Satellite Tokamak Programme Project
    -Construction Activities of JT-60SA Tokamak Progressing toward Assembly-
  7. 4-7 Accurate Fabrication of Large Superconducting Coil
    -Fabricating the Superconducting Coil for JT-60SA-
  8. 4-8 Manufacturing the Doughnut-Type Vessel for JT-60SA
    -High-Precision Structure of Double-Wall Vacuum Vessel-
  9. 4-9 Progress in Stability Theory for Rotating Plasmas
    -New Matching Theory for Resistive Wall Modes-
  10. 4-10 Lithium Isotope Separation for Fusion Reactor Fuel
    -Development of Innovative Technology for Lithium-6 Enrichment Using an Ionic Liquid-
  11. 4-11 Toward Clarifying Complex Plasma Behavior
    -Development of an Integrated Simulation Code for Entire Tokamak Plasma-
  1. 5-1 Large Increase in the Maximum Energy of a Laser-Driven Proton Beam
    -40 MeV Proton Generation Using a Ti:sapphire/OPCPA Hybrid Laser System-
  2. 5-2 High-Power γ-ray Generation via the Radiation Reaction Effect Using an Ultra-Intense Laser Pulse
    -Proposal for a New Laser-Driven γ-ray Source-
  3. 5-3 High-Precision Measurement of Nuclear Materials
    -Proposal for the Advanced HKED System-
  4. 5-4 Neutron Observation of Deformation Behavior of Materials at Cryogenic Temperature
    -Neutron Strain Measurement of a Superconducting Wire under Cryogenic Tensile Loading-
  5. 5-5 Discovery of Novel Rare-Earth Metal Hydrides under High Pressure
    -Formation of NaCl-Type Monohydrides by Pressure-Induced Phase Separation-
  6. 5-6 Microscopic Magnetization Process in a Tb43Co57 Amorphous Film Using Magnetic Compton Scattering
    -New Measurement Method for Spintronics Materials-
  7. 5-7 Development of a Microfabrication Technique for Utilization of Environmentally Friendly Plastics
    -Micro-/Nano-Fabrication of Crosslinked Poly(L-lactic acid) Using EB Nanoimprint Lithography-
  8. 5-8 Contribution to the Elucidation of the Mechanism of O2 Generation from Water Using Ce(IV)
    -Discovery of Dinuclear Complexes of Tetravalent Cerium in an Aqueous Solution-
  9. 5-9 Developing a Technique for Operating a Protein Assembly
    -Identification of the Key Residue Controlling Protein Assembly via X-ray Crystallography-
  10. 5-10 Phase Retrieval from Sparse Diffraction Data
    -Coherent X-ray Diffraction Imaging of Single Particles-
  11. 5-11 Drastically Altering the DNA of Plants
    -Ion Beams near the Range End Frequently Induce Large Deletions-
  1. 6-1 Accurate Evaluation of the Fuel Failure Limit
    -Improved Application of NSRR Test Data to Power Reactor Conditions-
  2. 6-2 Assessing the Failure Resistance of Reactor Pressure Vessels
    -Structural Integrity of Reactor Pressure Vessels Based on Probabilistic Fracture Mechanics Considering the Effect of Residual Stress-
  3. 6-3 Evaluation of the Confinement Safety of Radioactive Materials during a Fire
    -Acquisition of Combustion Data and Evaluation of the Clogging of the HEPA Filter-
  4. 6-4 Reactions for Determining Chemical Environments in Radioactive Waste Repositories
    -Corrosion Reaction of the Steel Overpack for High-Level Radioactive Waste-
  1. 7-1 First Observation of 239Pu Nuclear Magnetic Resonance
    -Elucidation of the Electronic State in Pu Compounds-
  2. 7-2 Generating Magnetic Flows with Sound
    -Discovery of a Link between Sound and Modern Spintronics-
  3. 7-3 Development of a New Method for Preparing Atomically and Electronically Uniform Graphene
    -Significant Progress for Spintronic and Nanoelectronic Applications-
  1. 8-1 Challenge of Obtaining Accurate Nuclear Data for Radioisotopes
    -Measurement of Neutron Capture Cross Sections of 244Cm with ANNRI-
  2. 8-2 Research on Boiling Heat Transfer Mechanism
    -Development of Simultaneous Measurement Technology for Surface Heat Flux and Surface Temperature-
  3. 8-3 More Precise Estimation of Reactor Decay Heat
    -JENDL/FPD-2011 and JENDL/FPY-2011-
  4. 8-4 Development of Database for a Practical Fuel Design
    -Formulation of Thermal Conductivity of Zr-Based TRU Nitride Fuels-
  5. 8-5 Analysis for Safety Assessment of Radwaste Disposal
    -Validation of Calculated Values of Content of Difficult-to-Measure Nuclides 79Se and 135Cs-
  6. 8-6 Removal Mechanism of Radiation-Induced Nucleotide Damage
    -Simulation Study of the Mechanism of Molecular Recognition by the Enzyme MutT-
  7. 8-7 Prediction of Radiation Damage in Accelerator Facilities and Nuclear Power Plants
    -Development of Radiation Damage Model for Various Particles-
  1. 9-1 Explore the Ultimate Nuclear Reactor That Is Safe Even If Accidents Occur
    -Conceptual Design Study of a Naturally Safe HTGR-
  2. 9-2 Spontaneous Stabilization of HTGRs without Reactor Scram and Core Cooling
    -Safety Demonstration Tests Using the HTTR: Loss of Reactivity Control and Core Cooling-
  3. 9-3 Design Criteria of HTGRs for Withstanding Extreme Events
    -Investigation of Technical Feasibility for Naturally Safe HTGRs-
  1. 10-1 Analysis of Transuranium Nuclides in Radioactive Waste
    -Analysis of Am and Pu in Contaminated Metal Surface-
  2. 10-2 Prevention of Heavy Metal Elution from Solidified Forms of Incinerated Ash and Cement
    -Confinement of Heavy Metals Using Insolubilizers-
  1. 11-1 How Does Impurity Diffuse in Irradiated Materials?
    -Evaluation of Impurity Segregation by Diffusion Rate Equations Based on the Atomic Migration Mechanism-
  2. 11-2 J-PARC and Supercomputer, a Collaborative Challenge to Solve the Mechanism of Superconductivity:
    -A Quest for Electron Pairing through Computer Simulation of Neutron Scattering in Iron-Based Superconductors-
  3. 11-3 How Do Earthquake Waves Propagate into a Nuclear Facility?
    -Realization of Precise Simulation of Building-Equipment Interaction during Earthquakes-
  1. 13-1 Reuse and/or Recycle of Dismantled Objects
    -Wet Blast Decontamination Technology-
  2. 13-2 Improved Reliability of Hand Dosimetry
    -Development of a Ring-Type Dosemeter Using Optically Stimulated Luminescence Elements (OSLRD)-
  3. 13-3 Effective Utilization of Concrete Debris Generated from Nuclear Reactors
    -Clearance of Concrete Debris Generated from Modification Work on JRR-3-
  4. 13-4 Separation and Recovery of Long-Lived Nuclides for Reduction of Radioactive Waste
    -Behavior of Oxidation and Extraction of Neptunium in Simplified Solvent Extraction Process-
  5. 13-5 Scintillation Neutron Detectors with a High Spatial Resolution
    -Position-Sensitive Detectors for Single-Crystal Diffractometer in J-PARC-
  6. 13-6 Visualizing Magnetic Fields Using Neutrons
    -Magnetic Field Imaging Technique Using Polarized Pulsed Neutrons-
  7. 13-7 Realizing a 1 MW High-Power Proton Beam
    -Beam Loss Reduction by Injection Painting in J-PARC RCS-
  8. 13-8 First HTGR Demonstration
    -First Achievement of a Continuous Supply of High-Temperature Nuclear Heat-
  9. 13-9 Development of a Dissimilar Metal Joint of Zircaloy-2 and 316L Stainless Steel
    -Application to Power Ramping Test of LWR Fuel in JMTR-
  10. 13-10 Corrosion Issues in Sodium Environment
    -Effects of Sodium on Structural Materials for Fast Breeder Reactors-
  11. 13-11 Chemical-State Observation of Microparticles
    -Microscopic Imaging of Luminescence Induced by Scanning Ion Microbeam-
  12. 13-12 Shafts Excavated to -500 m Depth
    -Construction of Shafts and Research Tunnels and Confirmation of Reduced Groundwater Inflow at the Mizunami Underground Research Laboratory-
  13. 13-13 Progress in Methodology Considering γ-ray Shielding Effects
    -Development of Simplified Calculation Method for Heterogeneously Distributed Radioactive Waste Drums-
  1. 1-1 Japan's Initiative for International Harmonizing of Safety Standards
    -Establishment of Safety Design Criteria for Sodium-Cooled Fast Reactors-
  2. 1-2 Safety Evaluation of Core Disruptive Accidents
    -Development of Level-2 PSA Methodology for FBRs-
  3. 1-3 Residual Heat Removal Using Buoyancy Force
    -Evaluation Method for Core Hot Spot under Natural Circulation-
  4. 1-4 Reliability of Recovery Operation for Reactor Trip Failure
    -Evaluation of "MONJU" Accident Management by Employing Probabilistic Safety Assessment Technique-
  5. 1-5 Toward Extending the Service Life of Fast Breeder Reactor Plants
    -Evaluation of Aged and Repaired Welded Joints-
  6. 1-6 Enhancement of Safety and Economic Competitiveness of Fast Breeder Reactor Plant
    -Steel Plate Reinforced Concrete Containment Vessel-
  7. 1-7 Validation of JENDL-4.0 with "MONJU" Reactor Physics Data
    -241Am Data Testing by Cross-Section Adjustment Technique-
  8. 1-8 Manufacturing MOX Raw Powder Uniformly and Effectively by Controlling Electromagnetic Waves
    -Study on Highly Effective Microwave Heating-
  9. 1-9 Research on Mechanical Properties of Fuel Claddings for High Burnup in Fast Breeder Reactors
    -Effects of Neutron Irradiation on Mechanical Properties of ODS Steel Claddings-
  10. 1-10 Technology for Removal of Excess Oxygen from MOX Fuels during Irradiation
    -Research and Development for MOX Fuel by Using Oxygen Getter-
  11. 1-11 For Effective Fuel Dissolution in Reprocessing
    -Development of Simulation Code for FBR Spent Fuel Dissolution-
  12. 1-12 Selective Electrochemical Dissolution of Spent Fuel
    -Behavior of Anodic Dissolution of U-Pu-Zr Alloy during Pyrochemical Reprocessing-
  13. 1-13 A New Extraction Process for Future Reprocessing
    -Development of Uranium and Plutonium Co-Recovery Process (Co-Processing Process)-
  1. 2-1 Transfer of Knowledge of Geoscience Technology
    -Information Synthesis and Interpretation System (ISIS)-
  2. 2-2 Evaluation of Uplift/Erosion Scenarios in the Far Future
    -Analysis Reflecting a Feature of Geomorphic Change in Japan-
  3. 2-3 First Release of Overpack Database
    -Information on Overpack Designing and Manufacturing and Experimental Data are Provided Intelligibly-
  4. 2-4 Revealing the Pore Structure and Diffusion Mechanism in Rock
    -Analysis of Pore Structure of Siliceous Mudstone Using Nano X-ray Computed Tomography-
  5. 2-5 Predicting the Future from Ancient Tectonism
    -History of Fault Development in Fractured Rocks-
  6. 2-6 Challenges in Collecting Nanoscale Particles from Groundwater
    -Development of New Ultrafiltration Techniques Maintaining In situ Pressure and Anaerobic Conditions-
  7. 2-7 Understanding Regional Stress in a Rock Mass
    -Estimation of Regional Stress Using Measured Stress-
  8. 2-8 Rock Mass Response to Shaft Excavation
    -Fault System Controlling Rock Mass Behavior in Soft Sedimentary Rocks-
  9. 2-9 Improvement in Reliability of Geological Disposal Technology
    -Use of Low-Alkaline Cement in the Construction of a Gallery-
  10. 2-10 Investigation of Shallow Groundwater Migration at Snowy Cold Region
    -Research of Shallow Groundwater Flow Based on Groundwater Level and Geological Structures in the Horonobe Area-
  1. 3-1 Significant Progress in ITER Coil Procurement
    -Mock-Up Trials for ITER Toroidal Field Coils-
  2. 3-2 H- Beam Acceleration Close to ITER Requirement
    -Development of 1 MeV Accelerator for ITER Neutral Beam Injector-
  3. 3-3 Fulfillment of ITER Criteria for RF Energy Transmission Efficiency
    -Development of Electron Cyclotron Heating and Current Drive for ITER-
  4. 3-4 Innovative In-Vessel Mirror for Current Profile Measurement in ITER
    -Development of Retroreflector for ITER Poloidal Polarimeter-
  5. 3-5 Progress in Satellite Tokamak Programme Project as part of Broader Approach Activities
    -Construction Activities of JT-60SA Tokamak Right on Track-
  6. 3-6 Observation of Multistage Transition in Radial Electric Field
    -A New Discovery Unexpected in the Case of the Standard Model-
  7. 3-7 Planning and Executing Joint Experiments, Leading International Team
    -Toward Validation of Neutral Beam Current Drive Theory for ITER-
  8. 3-8 Exploring the Possibility of Inducing Plasma Rotation by Fusion Reactions
    -Intrinsic Torque Generation by α-Particles-
  9. 3-9 Early Realization of Fusion Reactor
    -International Fusion Energy Research Centre Project in the Broader Approach Activity-
  10. 3-10 Study on Formation of Temperature Profile of Plasma Core
    -First-Principles Simulation of Plasma Transport-
  11. 3-11 Manufacture of Small Tritium Target for Use in Generating Neutrons in Fusion Reactor at JAEA
    -Stable Procurement of Small Tritium Targets-
  12. 3-12 Validation of Fusion Reactor Materials
    -Design and Construction of IFMIF/EVEDA Li Test Loop-
  1. 4-1 Toward the Realization of the Strongest and Brightest Electron Source in the World
    -Development of a 500-kV Photocathode DC Electron Gun for Realizing Next-Generation Light Source-
  2. 4-2 Improvement of the Reflectivity of Relativistic Flying Mirrors
    -Demonstration of Efficient Reflection of Laser Light from Plasma Waves-
  3. 4-3 Evaluation of Polarization of Soft X-rays
    -Soft X-ray Optics and Polarization Analysis-
  4. 4-4 Development of Spin Contrast Variation Technique
    -Verification Study with a Simplified Model System-
  5. 4-5 Clarification of Hidden Electronic Character Using Synchrotron Radiation X-ray
    -Orbital State of Excited Electron Identified by Polarization-Analyzed Resonant Inelastic X-ray Scattering-
  6. 4-6 Toward Domain Observation Using Coherent X-rays
    -Multiple-Length-Scale Approach Revealing the Nature of High-Functional Solids-
  7. 4-7 Mechanism of Performance Improvement of Hydrogen Storage Materials
    -Structural Determination of Additives by X-ray Absorption Spectroscopy-
  8. 4-8 Development of Novel Rare-Earth-Recognition Compound
    -For Efficient Separation and Purification of Rare-Earth Elements-
  9. 4-9 How to Produce Rare-Earth Metals by Ourselves?
    -Recovery of Rare-Earth Metals from Hot Springs-
  10. 4-10 Purification of Factory Waste Gases Using By-Products Ozone
    -Electron Beam/Catalyst System for Purification of Waste Gases under Practical Gas-Flow Conditions-
  11. 4-11 Low-Barrier Hydrogen Bond in Protein
    -Neutron Protein Crystallography Casts Light on a New Factor Important of Drug Design-
  12. 4-12 Role of Electric Fields Produced by Heavy-Ion Irradiation in DNA Damage
    -Is Occurrence of Clustered DNA Damage Promoted by the Electric Fields?-
  13. 4-13 Persistent Chromosomal Aberration Caused by Ionizing Radiation
    -Appearance of Micronuclei in Descendants of γ-ray-Irradiated Plant Cells-
  1. 5-1 Origin of Hydrogen Embrittlement of Fuel Claddings
    -Calculation of Hydrogen Effect on Resistance to Crack Propagation-
  2. 5-2 Evaluating Safety Performance of Oxidized Fuel Cladding
    -Investigation of Test Methods for Evaluating Fuel Integrity in Loss-of-Coolant Events-
  3. 5-3 For Reliable Evaluation of Corrosive Conditions in Reactor Core
    -Enhancement of Technology for Water-Chemistry Evaluation-
  4. 5-4 Research on Corrosion Resistance of Reactor Pressure Vesse
    -Evaluation of Degradation of Thermally Affected Stainless Steels by Microstructural Analysis-
  5. 5-5 Development of Evaluation Method for Crack Growth Associated with Large Earthquakes
    -Accurate Prediction of the Crack Growth Rate of Piping Materials-
  6. 5-6 Core Power Stability under Strong Earthquake
    -Neutron-Coupled Thermal Hydraulic Calculation under Seismic Acceleration-
  7. 5-7 How to Evaluate the Radioactivity in a Nuclear Reactor under Operation?
    -System Development for Evaluating the Radioactivity in the Reactor-
  8. 5-8 Estimation of Gaseous Iodine Revolatilization under Severe Accident Conditions
    -Application of Iodine Chemistry Reactions to Plant Evaluation-
  9. 5-9 What Accelerates Dissolution of High-Level Waste Glass?
    -Effects of Magnesium Ions in Solution-
  10. 5-10 Toward Safe Decommissioning of Nuclear Facilities
    -Development of Safety Assessment Code for Decommissioning Activities-
  1. 6-1 Magnetic Flow Turns Electronics into Spintronics
    -Discovery of New Principles for Generating Spin Currents-
  2. 6-2 Detection of Electron Spins in Ferromagnets Using Spin-Polarized Positron
    -Development of Highly Spin-Polarized Positron Beam-
  3. 6-3 Discovery of New Type of Fission
    -The Fission of 180Hg is not Influenced by the Shells of Fragments-
  4. 6-4 Unconventional Superconductivity in Uranium Compounds
    -Correlation between the Anomalous Electron Scattering and Superconductivity in URu2Si2-
  5. 6-5 Biological Nanoparticle Production Factory
    -Recovery of Heavy Elements by Using Microorganisms-
  1. 7-1 Nuclear Polarization Controlled by a Laser Beam
    -Dynamic Nuclear Self-Polarization Induced by Circularly Polarized Light-
  2. 7-2 Simulated Melting and Solidification of Metal
    -Extension of Mechanistic Liquid-Gas Two-Phase Flow Analysis Method-
  3. 7-3 Approach for Realization of Transmutation Technology
    -Issues Pertaining to Reactor Design for Accelerator-Driven System-
  4. 7-4 Change in Fuel Microstructure Induced by Helium Accumulation and Release
    -Expansion and Annealing Correlation for Lattice and Bulk-
  5. 7-5 Great Challenge of Separation of Minor Actinides by Solvent Extraction
    -Trial Use of Hydrophilic and Lipophilic Diamides-
  6. 7-6 How Hydrophilic are Actinide Ions?
    -Determination of Standard Gibbs Energy of Transfer at Aqueous/Organic Interface-
  7. 7-7 Prediction of Irradiation-Assisted Stress Corrosion Cracking of Structural Materials in Nuclear Reactors
    -Study on Material Degradation Diagnosis Method Using Magnetic Sensor-
  8. 7-8 Analysis of Isotopic Composition without Touching the Sample
    -Isotope Analysis of Nuclear Fuel Using Resonance Absorption Spectrometry-
  9. 7-9 Towards Prediction of Dispersion of Hazardous Materials in Urban Area
    -Development of Local-Scale High-Resolution Atmospheric Dispersion Model-
  10. 7-10 Production of Medical RIs Using Accelerator Neutrons
    -Development of an Innovative RI Production Method-
  1. 8-1 Toward a Reactor with Highest Safety Standards
    -Development of HTGR Based on Inherent Safety Features-
  2. 8-2 Development of High-Pressure Ceramic Components for Hydrogen Production
    -Strength Estimation Method for Component Design-
  1. 9-1 Rational Decommissioning Planning
    -Development of Project Management Data Evaluation System-
  2. 9-2 Development of Decontamination Technique for Radioactive Wastes Using Supercritical Fluid
    -Reverse Micelle Formation in Supercritical Carbon Dioxide-
  3. 9-3 Toward Analysis of Radionuclides in Solidified Products
    -Preparation of Reference Materials Containing Volatile Nuclides-
  1. 10-1 Determination of Properties of Nuclear Fuels through Numerical Simulation
    -First-Principles Calculations of Electronic States of Plutonium Dioxide-
  2. 10-2 Solving the Mystery of Hydrogen-Induced Strength Degradation
    -Development of Atomic-Scale Model of Hydrogen and Iron Atoms-
  3. 10-3 Finding Important Information in Experimental or Simulation Results
    -Proposal of Visualization Technique for Capturing Temporal and Spatial Fluctuations-
  4. 10-4 Understanding Fluid Motion in a Spent Fuel Pool
    -Proposal of Fluid Analysis Model including Turbulent Effect near Surfaces and Walls of Pool-
  1. 11-1 Evaluation of Japan's Nuclear Non-proliferation Efforts in Terms of Providing Guidance to Other States
    -Key Elements to Win the Confidence in the Peaceful Nature of the Nuclear Energy Use and Recommendations for the Future-
  1. 12-1 What Was Acquired from Restarted "MONJU" Operation
    -Results of the "MONJU" Core Confirmation Test-
  2. 12-2 Low-Cost and Labor-Saving Method for Replacement of Acrylic Panels of a Large Glove Box
    -Innovative Panel Replacement Technique Using Bag-In/Bag-Out Method-
  3. 12-3 Removal of Liquid Impurities in Crystal by Sweating
    -Purification of Uranyl Nitrate Hexahydrate Crystal by Isothermal Sweating Effect-
  4. 12-4 Effective Preparation of MOX Pellets
    -Development of a New Method for Fabricating MOX Pellets Having Low Oxygen-to-Metal Ratio Using Residual Carbon-
  5. 12-5 Precise Control of High-Intensity Proton Beams
    -Beam Handling by the Digital Low-Level RF Control System-
  6. 12-6 Polarizing the Spins of Pulsed Neutron Beams
    -Development of Neutron Polarizing Devices for J-PARC-
  7. 12-7 Improving the Safety of Liquid-Metal Facilities
    -Countermeasures for Lithium Leak in the IFMIF/EVEDA Lithium Test Loop-
  8. 12-8 Viewing the Behavior of Fuel Pellets
    -Irradiation Behavior Investigation of FBR Fuel by High-Resolution X-ray CT-
  9. 12-9 Challenges to Domestic Production of 99Mo Using JMTR
    -Development of a New Mo Adsorbent for 99Mo-99mTc Generator-
  10. 12-10 Expansion of Measurable Dose Range
    -Development of Dosimetry for Quality Assurance in Radiation Processing-
  11. 12-11 Excavation of Research Tunnels Deep Underground
    -Excavation and Construction of Shafts and Tunnels at the Mizunami Underground Research Laboratory-
  12. 12-12 A Trial for Uranium Wastes Assay Used Neutrons!!
    -Developments of NDA Tools of Uranium Wastes Drums: NWAS-
  1. 1-1 A Reliable Cooling System for a Commercial FBR
    -Double Wall Boundary Design Advancing a Commercial FBR-
  2. 1-2 What Core Design Prevents Nuclear Proliferation?
    -Commercial FBR Core Study Focusing on a Material Barrier-
  3. 1-3 For Advanced Safety of Next-Generation FBRs
    -Elimination of Severe Power Burst Events in Core Disruptive Accidents-
  4. 1-4 The Challenge of Detecting Small Defects in SG Tubes
    -3D Numerical Simulations of ISI of FBR SG Tubes Using ECT-
  5. 1-5 Reliable Separation of Fuel Pins from the Fuel Assembly
    -Development of Mechanical Disassembly Technology for FBR Spent Fuel-
  6. 1-6 Chemical Separation Process Resistant to Decay Heat from Radionuclides
    -Extraction Chromatography System for Minor Actinides Recovery-
  7. 1-7 Advanced Particle Flowability Measurement for Nuclear Fuel Pellet Production
    -Investigation of the Applicability of a Vibrating Tube Method Using Model Particles-
  8. 1-8 Representing the Irradiation Behavior of FBR Fuel
    -Development of Np- and Am-Bearing MOX Fuel-
  9. 1-9 Investigation of Compounds in the PuO2-SiO2 System
    -Behavior of Si Impurity Contained in MOX Fuel-
  10. 1-10 Simultaneous Recovery Technique for Uranium and Transuranic Elements Using Molten Salt Media
    -Development of Metal Electro-Refining Pyrochemical Reprocessing-
  11. 1-11 Monitoring Irradiation Damage in Reactor Structures
    -Development of an Irradiation Damage Evaluation Method Using Magnetic Measurement-
  12. 1-12 The Challenge to Control the Chemical Reactivity of Liquid Sodium
    -Development of Reactivity Control Using an Atomic Interaction between Nanoparticles and Sodium-
  1. 2-1 Prototype Knowledge Management System
    -Challenges for Knowledge and Technology Transfer-
  2. 2-2 Development of a Coupled THMC Model
    -Engineered Barrier Experiment and Analytical Studies Focused on Geochemical Processes in Bentonite Buffer Material-
  3. 2-3 Evaluating the Solubility of Radionuclides with Speciation in Groundwater
    -Development of the Thermodynamic Database for Safety Assessment of Geological Disposal-
  4. 2-4 Modeling of Radionuclide Migration in Actual Surface and Near-Surface Environments
    -Approach to Develop a Biosphere Model for Geological Disposal Safety Assessment-
  5. 2-5 Exploring Chemical Environments 1000 m Underground Using Microbiological Characterization
    -In Situ Microbiological Properties of Toki Granite-
  6. 2-6 Elucidating Crustal Evolution
    -Inferred Formation of Granitic Rock Based on 3D Petrological Evidence-
  7. 2-7 Heat Source for Hot Springs in the Noto Peninsula
    -An Amagmatic Hydrothermal System in a Non-Volcanic Region-
  8. 2-8 Establishment of a Practical Guide for Construction Management in Deep Shaft Sinking
    -A Rock Mass Behavior Classification Proposal for Deep Shaft Sinking-
  9. 2-9 Deformation and Failure Behavior in Deep Sedimentary Rocks
    -Evaluation of Sedimentary Rocks Based on Laboratory Tests-
  10. 2-10 Estimating Long-Term Changes in Deep Subsurface Hydrochemical Conditions
    -Research into Water - Mineral - Microbe Interactions-
  1. 3-1 Start of Manufacture of the Superconductors for the ITER Magnets
    -Development of Exacting Quality Assurance Techniques-
  2. 3-2 Development of an In-Vessel Remote Handling Robot for the ITER
    -Demonstration for Automatic Assembly and Installation of the Remote Handling Robot-
  3. 3-3 Demonstration of Voltage Holding with the World?s Largest Fine Ceramic Ring
    -Progress on Development of a 1 MV Accelerator for Heating and Current Drive in ITER-
  4. 3-4 Robust Leak Tight Box with Thin Wall Membrane Structure
    -Demonstration of a Tritium Breeder Pebble Container for the ITER Test Blanket Module-
  5. 3-5 Progress in the Satellite Tokamak Program Project for Broader Approach Activities
    -Europe-Japan Joint Construction of the JT-60SA Tokamak Launched-
  6. 3-6 High Energy and Large-Area Negative Ion Beams Successfully Produced
    -Progress with the JT-60SA Neutral Beam Injector-
  7. 3-7 New Instability Observed in High Pressure Plasmas
    -Exploitation of Stability Physics toward High Pressure Burning Plasmas-
  8. 3-8 Investigating Complex Patterns of Tokamak Edge Plasma Flow
    -Pioneering Plasma Physics with First-Principles Advanced Particle Simulation-
  9. 3-9 Investigation of Impurity Transport in Plasma
    -Development of Accurate Quantitative Analysis for Tungsten on the Plasma Facing Wall-
  10. 3-10 Further Improvement of the Fusion Reactor Structural Material
    -Inclusion Control in Reduced Activation Ferritic/Martensitic Steel F82H-
  11. 3-11 For Validation of Materials for the Fusion DEMO Reactor
    -Development of Small Specimen Test Technology in the International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities (IFMIF/EVEDA)-
  1. 4-1 Success in Gaining a New Insight into High-Temperature Water under Pressure
    -Toward Full Understanding of Water-
  2. 4-2 Observation of Tunnel Ionization from an Orbital Lower than HOMO
    -First Determination of Ionized Orbital by Comparing the Experiment with the Computer Simulation-
  3. 4-3 Direct Observation of Fermi Surfaces Formed by Heavy Electrons
    -Clue to the Mechanism of Anomalous Superconductivity Coexisting with Magnetism-
  4. 4-4 Observation of Dynamical Surface Morphology with One-Nanometer Resolution
    -Development of the Soft X-ray Laser Interferometer-
  5. 4-5 Behavior of Metal Fine Particles during Automotive Emissions Control
    -Direct Observation of a Catalytic Reaction by Time-Resolved X-ray Absorption Spectroscopy-
  6. 4-6 Supernova Neutrino-Process Nucleosynthesis
    -Astrophysical Origin of 180Ta, the Rarest Nuclide in the Solar System-
  7. 4-7 Kerogen as a Noble Gas Carrier Phase of Meteorite
    -The Origin of the Solar System Revealed by Synchrotron Radiation-
  8. 4-8 New Graft Polymerization of High Performance Polymer Electrolyte Membrane
    -Synthesis of Block Graft Type Membrane by Radiation / Living Graft Polymerization-
  9. 4-9 Semiconductor Devices Can Be Operated in Harsh Radiation Environments in Nuclear Plants
    -Development of SiC Transistors Having Radiation Hardness-
  10. 4-10 Inspection and Repairing Welding System for an Inner Tube Wall
    -Combination Laser Processing Technique and Eddy Current Testing-
  11. 4-11 Elucidation for Catalytic Mechanism of Elastase by Neutron Diffraction
    -Success in Observing the Oxyanion Hole in Serine Protease-
  12. 4-12 Global Conformational Changes of Ribosome Revealed from Low-Resolution Structural Data
    -A New Technique for Building Molecular Models from Electron Microscopy Data-
  13. 4-13 Development of a Novel Radiopharmacutical Finding Even Very Small Tumors
    -Success in PET Imaging of Pheochromocytomas Using 76Br-MBBG-
  1. 5-1 Demonstration of a New Method for Ion Acceleration Aiming at a Development of a Compact Laser-Driven Hadron Therapy System
    -Ion Acceleration Using Subcritical-Density Plasma Created Using a Nanoparticle Target-
  2. 5-2 Unlimited Particle Acceleration by Photon Pressure Was Proposed
    -Synchronized Thin Foil Plasma Acceleration Due to Photon Pressure-
  1. 6-1 Toward Fuel Safety Regulations with Improved Rationality
    -Study of High Burnup Fuel Behavior in RIA Using the NSRR High Temperature Capsule-
  2. 6-2 Evaluation of Thermal Properties of High Burnup MOX Fuel for LWRs
    -Thermal Conductivity Change in MOX Pellets Due to Long-Term Use-
  3. 6-3 For Safe and Long-Term Utilization of Control Rods
    -Evaluation of the Properties of Hafnium-
  4. 6-4 Toward Safe Long-Term Service of Reactor Pressure Vessels
    -Prediction of the Service Life Based on Nano-Scale Structural Analysis-
  5. 6-5 Assessing the Structural Integrity of Reactor Pressure Vessels
    -Fracture Mechanics Assessment Considering the Effect of Weld-Overlay Cladding-
  6. 6-6 Which Model Inputs Are More Important?
    -Development of a New Importance Measure and the GSALab Code-
  7. 6-7 How Much Radioiodine Is Released in a Severe Accident?
    -Chemical Production of Volatile Iodine in Radiation Conditions-
  8. 6-8 Analysis Method Validation and Criticality Data Production
    -Revision of Data Collection for the Nuclear Criticality Safety Handbook-
  9. 6-9 Mass Transport Retardation Studies in Bedrock
    -Sorption Experiments under Anoxic Conditions-
  1. 7-1 Analyzing Supherheavy Atoms on an Atom-at-a-Time Scale
    -Oxidation of Nobelium with Flow Electrolytic Chromatography-
  2. 7-2 Challenges for the Mysterious Properties in the Uranium Compounds
    -New Physical Properties in a Super High Quality Single Crystal of URu2Si2-
  3. 7-3 Breakthrough for Isotope Separation
    -Separating Isotopes in Solids or Liquids Using a Centrifuge-
  4. 7-4 Exploring Amazing Functions of Microbes
    -Formation of Biogenic Nanoparticles of Precious Metals-
  5. 7-5 A Novel Technique for Investigating Radiation Damage in DNA
    -Selective Induction of DNA Damage by Synchrotron Soft X-rays-
  1. 8-1 New Nuclear Data Library for Science and Technology
    -General Purpose Japanese Evaluated Nuclear Data Library JENDL-4.0-
  2. 8-2 Operation of the Accurate Neutron-Nucleus Reaction Measurement Instrument Has Been Started
    -To Obtain More Accurate Nuclear Data-
  3. 8-3 Microscopic Observation of Deformation Process in Metallic Materials
    -Computer Modeling of Defect Structure via Atomistic Simulation Methods-
  4. 8-4 Rationalization of the Structural Design of Nuclear Components under Exposure to Intense Irradiation
    -Development of a Concept for Assuring Integrity Applicable to Components with Reduced Ductility Due to Intense Irradiation-
  5. 8-5 To Clarify Material Characteristics from the View Point of Microstructure
    -Image Based Modeling of Ceramic Material Using X-ray CT-
  6. 8-6 High Performance Extraction Separation Systems Using Ionic Liquids
    -Application to Extraction of Metal Ions and Proteins-
  7. 8-7 How Does Radiation Influence Cells, the Human Body, and the Earth?
    -Integration of Radiation Transport Simulations for Different Scales-
  8. 8-8 Simple and Low-Cost New Recovery Technology “Emulsion Flow”
    -Extending Radioactive Liquid Waste Treatment to Effluent Purification Technology-
  1. 9-1 Toward Efficient Hydrogen Production in IS Process
    -Development of a Radiation-Grafted Membrane for HI Concentration-
  2. 9-2 Towards a Stable Operation of Nuclear Hydrogen Production Systems
    -Sequence Control Against Abnormal Events in Hydrogen Production Plants-
  1. 10-1 Advanced Treatment Technology for Low-Level Radioactive Reprocessing Effluent
    -Aiming at Establishing Cement-Based Encapsulation Technology-
  1. 11-1 Toward Effective Judgment of Clearance
    -Developing a Program for Selection of NMAs-
  2. 11-2 Reasonable Uranium Waste Disposal
    -Safety Assessment for Sub-Surface Disposal of Uranium Waste-
  3. 11-3 Analytical Techniques for Radioactive Nuclides in Wastes Generated from Research Facilities
    -Guidelines for a Simple and Rapid Determination Method for Waste Samples-
  1. 12-1 Toward Execution of Long-Time Atomic Energy Simulations
    -Development of Fundamental Technology that Easily Executes Large-Scale Simulations-
  2. 12-2 Development of Fast Eigenvalue Solver on a Cell Cluster
    -Toward Real Time Plasma Stabilization on ITER-
  3. 12-3 Improving Material Degradation Simulation Using Evolutional Mechanism
    -Application of Genetic Algorithms to the Production of Polycrystal Structures-
  4. 12-4 Curious Characters of Iron-Based Superconductors
    -R&D for Application Based on Their Unique Features-
  1. 13-1 Toward Advanced Safeguards of Future Nuclear Fuel Cycle Facilities
    -Development of Safeguards Verification Technologies for Large Pu-Throughput Facilities with Treating Low-Decontaminated, MA-Bearing Nuclear Material-
  1. 14-1 Monitoring Sensors by Optical Fiber Grating
    -Application of Femtosecond Laser Processing for the Piping System-
  2. 14-2 Development of Capacitance Void Fraction Meter for LWR Test
    -Measurement under High Temperature and High Pressure Conditions-
  3. 14-3 Toward Highly Purified Uranyl Nitrate Hexahydrate Crystal
    -Physicochemical Properties of Plutonium Cesium Nitrate-
  4. 14-4 Improvement of Pu and U Measurement Reliability
    -The First ISO Accreditation of a Testing Laboratory for Nuclear Materials in Japan-
  5. 14-5 Neutrons Clarify the Full Picture of Atomic Motions
    -Novel Method for High Efficiency Inelastic Neutron Scattering Measurement Demonstrated in J-PARC-
  6. 14-6 Realization of the World?s Most Brilliant Neutron Source at J-PARC
    -Unique Source Design and Smooth Power-Up of Accelerators-
  7. 14-7 Development of Hydrogen Production Technique
    -A Thermo-Chemical and Electrolytic Hybrid Hydrogen Production Process-
  8. 14-8 Remote Inspection in the Reactor Vessel by Optical Fiber
    -In-Vessel Observation in JOYO-
  9. 14-9 3-Dimensional Floating Support System to Permit of Thermal Expansion and Decrease of Thermal Stress
    -Establishing an Evaluation Method for Thermal Displacement Behavior-
  10. 14-10 Quick Change of Micron-Size Ion Beam
    -Integration of Cocktail Beam Acceleration and Microbeam Formation Techniques-
  11. 14-11 Going Deeper than -400 m Underground
    -Construction of Shafts and Research Tunnels and Method for Reducing Water Inflow at the Mizunami Underground Research Laboratory-
  12. 14-12 Development of Environmentally-Friendly Technique for Treating Radioactive Waste
    -Development of Uranium Recovery Technique Using Ionic Liquids-
  13. 14-13 Contribution to Producing a Certificated Reference Material by AMS MUTSU
    -Result of an Interlaboratory Comparison by the IAEA-
  1. 1-1 Commercial Fast Reactor Concept with Improved Economy
    -R&D of Innovative Technologies and Their Application to Plant Design-
  2. 1-2 Improvement in Environmental Burden Reduction of Advanced FBR
    -Core and Fuel Design Study for Minor Actinide Containing Oxide Fuel-
  3. 1-3 Investigation of Irradiation Behavior of Future FBR Fuel
    -Short-Term Irradiation Behavior of Am-Containing MOX Fuel-
  4. 1-4 Numerical Simulation of Time-Dependent Thermal Interaction between Fluid and Structure
    -Thermal Mixing in T-Junction Piping System-
  5. 1-5 Sophisticated Design Concept for FBR Components
    -Evaluation of Creep Design Region by Negligible Creep Curve-
  6. 1-6 Efforts to Improve Monitoring of High Temperature Piping
    -Development of Pipe Wall Thinning Sensor-
  7. 1-7 Oxidation in Sodium Combustion Process
    -Role of Sodium Oxide Generated on Liquid Sodium-
  8. 1-8 Ultimate Behavior of Seismically Isolated FBR Plants in Huge Earthquake
    -Large Shaking Table Test of Horizontal Isolation System-
  9. 1-9 Effectively Dissolving Spent Fuels
    -Development of Rotary Drum Type Continuous Dissolver for FBR Fuel Reprocessing-
  10. 1-10 Simple Control of Valence of Actinide Element
    -Development of U-Pu-Np Co-Extraction Process-
  11. Toward the Commercialization of MOX Fuel Production by Simplified Pelletizing
    -Mechanism of Boiling Step in Innovative De-Nitration, Its Effect on Vessel Design-
  1. 2-1 Structuring Knowledge on Geological Disposal Technology
    -Development of a Knowledge Management System-
  2. 2-2 Study of Hydraulic Behavior in Rock Fractures
    -Quantitative Measurement of Flow in a Fracture by Optical Method-
  3. 2-3 Impact of a Fault Movement Across a HLW Repository
    -Observed and Calculated Barrier Shear Due to Fault Movements-
  4. 2-4 Development of Radionuclide Migration Database
    -Update of Sorption/Diffusion Database Categorized by QA-
  5. 2-5 Past Geological Events Discovered with 1mg of Carbon
    -Development of Dating Method with an Accelerator Mass Spectrometer-
  6. 2-6 Effective Groundwater Flow Modeling and Analysis
    -Development of Efficient Modeling and Analysis System for Complicated Groundwater Flow-
  7. 2-7 Searching for the Spatial Distribution of Rock Fractures
    -Modeling of Fracture Density Based on Geological Interpretation-
  8. 2-8 Estimation of Fracture Connectivity from One-Borehole Data
    -Fracture Investigation of Sedimentary Rocks-
  9. 2-9 Findings of Long-Term Groundwater Pressure Monitoring
    -Analysis of Groundwater Pressure Measurements in Sedimentary Rock-
  10. 2-10 Estimation of Excavation Stability from Measurements
    -Application of Observational Construction to Sedimentary Formations-
  1. 3-1 Successful Instability Suppression by Fast Turn-On/Off of 600kW Millimeter Waves
    -Demonstration of Effective Method for Instability Suppression in ITER-
  2. 3-2 Improved Precision of ITER Plasma Predictions
    -Parameter Determining Width of Edge Transport Barrier (ETB) Elucidated-
  3. 3-3 Study of Disruption Phenomena in Advanced Plasmas
    -Clarification of Plasma Flow and Multi-Stage Phenomena-
  4. 3-4 World Record in Longest Injection of High Power Neutral Beams above 1MW
    -Towards a 100s Injection for JT-60SA-
  5. 3-5 JAEA's Accelerator Chosen for ITER NBI
    -Comparative Test of Accelerators for Neutral Beam Injector-
  6. 3-6 Superconducting Magnet Technology in ITER
    -Development of the Largest Superconducting Magnet in the World-
  7. 3-7 Development of Diagnostics System for Divertor Plasma Control in ITER
    -Creating a Highly Reliable Optical Diagnostic System for the Harsh Environment of ITER-
  8. 3-8 Successful High Repetition Rate Operation of High Power Gyrotron
    -Simulating ITER Gyrotron Operation-
  9. 3-9 ITER Divertor Prototypes Pass High Heat Flux Test
    -Prototypes Fabricated by JAEA Withstand High Heat Flux-
  10. 3-10 Improvement of Prediction Accuracy of Neutron-Induced Heat in Fusion Reactor Materials
    -Measurement of Double-Differential Cross-Sections of Charged Particle Emission-
  11. 3-11 For Validation of Fusion Reactor Materials
    -Research and Development of Liquid Lithium Target for International Fusion Materials Irradiation Facility (IFMIF)-
  1. 4-1 Observation of Collective Behavior of Strongly Interacting Electrons
    -Study of Collective Charge Excitations of Charge Stripes-
  2. 4-2 Study of a Dilute Magnetic Semiconductor by Observing Soft X-ray Magnetic Circular Dichroism
    -Way to Improve Spintronics Material Performance Revealed by Synchrotron Radiation-
  3. 4-3 Toward a Hydrogen Utilizing Society
    -Hydrogenation of Aluminum with Hydrogen Fluid-
  4. 4-4 Advanced Prediction Methods of Satellite Lifetime
    -Radiation Degradation Modeling of New Outer Space Solar Cell-
  5. 4-5 Metal Oxides Become Active Catalysts When Irradiated by Electron-Beams!
    -Enhancement of the Oxidation of Organic Substances with Electron-Beam Irradiated γ-Alumina-
  6. 4-6 Controlling Molecular Vibration to Allow Laser Isotope Separation
    -Vibrational Control of Iodine Molecules by a Ultrashort-Pulsed Laser-
  7. 4-7 Application of γ-ray Beams Generated from Laser-Electron Interaction
    -Isotope-Specific Mapping of Heavily Shielded Objects-
  8. 4-8 Developing Effective Anti-HIV Drugs
    -Success in Determination of Positions of All Atoms in HIV-1 Protease-
  9. 4-9 Protein Dynamics Revealed by Neutron Inelastic Scattering
    -Watching Fluctuating Proteins-
  10. 4-10 Utilization of Atmospheric Nitrogen as Nutrition by Leguminous Plants
    -Imaging of Symbiotic Nitrogen Fixation Using a Positron-Emitting Tracer Imaging System-
  11. 4-11 Just 10 Heavy-Ions Induce Drastic Radiation Effect on a Million Cells
    -Analysis of Bystander Effect Using Heavy-Ion Microbeam-
  12. 4-12 New Drug for Concurrent Cancer Chemotherapy and Radiotherapy
    -Development of a Nano-Capsule Opened by Radiation-
  1. 5-1 Testing Environmental Assessment Models Using Chernobyl Data
    -Validation of OSCAAR Models for Assessing Accident Consequences-
  2. 5-2 Oxidation Behavior of Fuel Cladding Used for a Long Time
    -Influence of High Burnup on Oxidation Kinetics in LOCAs-
  3. 5-3 Why Does the Microstructure of Fuel Pellets Change during Irradiation?
    -Relationship between the Crystal Lattice Strain and Microstructural Change in UO2 Pellets-
  4. 5-4 Exploration of Droplet Cooling Effect on Superheated Fuel
    -Developing Models Estimating Post-BT Heat Transfer Coefficient and Rewetting Velocity-
  5. 5-5 Assessing the Structural Integrity of Reactor Piping in Large-Scale Earthquake
    -Effect of Weld Residual Stress and Excessive Loading on SCC Growth-
  6. 5-6 Development of Rapid Dose Evaluation Method for Criticality Accidents
    -High Dose Measurement of Neutrons with Thermo-Luminescence Dosimeter-
  7. 5-7 Verifying Safety of Coastal Radioactive Waste Disposal Site
    -Modeling of Mass Transport upon Chemical Reaction with Saline Groundwater-
  8. 5-8 Determining Groundwater Flow on a Regional Scale
    -A Study of a Regional Groundwater Flow System in a Sedimentary Rock Area-
  1. 6-1 Electronic Origin of Giant Magnetoresistance Effect in C60-Co Films
    -Spectroscopic Examination of Spin States in Organic-Transition Metal Materials-
  2. 6-2 New Fission Channel Opened in Reaction Using Deformed Nucleus 238U
    -Fission of Super-Heavy Nucleus 274Hs-
  3. 6-3 Identification of Magnetic Fluctuations Inducing Unconventional Superconductivity
    -Mechanism of Superconductivity Revealed by Nuclear Magnetic Resonance-
  4. 6-4 Probing Interstitial Hydrogen States Using Positive Muons
    -For Detailed Understanding of Rare-Earth-Based Hydrogen-Absorbing Alloys-
  1. 7-1 Validation of Accuracy of Prediction of Neutronic Behavior in a Design without Full-Scale Mock-Up Critical Experiments
    -Development of a Prediction Uncertainty Evaluation Method Using Results of Critical Experiments-
  2. 7-2 Improving Accuracy of Nuclear Transmutation Data
    -Measurement of Fast Neutron Capture Cross Sections-
  3. 7-3 Completion of Database Supporting Technological Basis for Spent Nuclear Fuel Reprocessing
    -Handbook on Process and Chemistry of Nuclear Fuel Reprocessing Ver.2-
  4. 7-4 Elucidation of Corrosion Mechanism of Stainless Steel for Spent Fuel Reprocessing Plants
    -Study of Corrosion Mechanism of Nitric Acid Solution Containing Neptunium-
  5. 7-5 Elucidating Thermal Change in Am-Containing Oxide Fuels
    -Investigation of Thermodynamic Properties of Nonstoichiometric Am Oxides-
  6. 7-6 Prediction of Atmospheric Dispersion of Radionuclides by Accidental Discharge in the World
    -Development of WSPEEDI-II: Worldwide Version of System for Prediction of Environmental Emergency Dose Information 2nd Version-
  7. 7-7 Effects of Body Posture on Dose Assessment
    -Analysis of Organ Doses Using Japanese Voxel Phantoms-
  8. 7-8 Toward Efficient Hydrogen Production by Thermochemical IS Process
    -Measurement of High Pressure Vapor-Liquid Equilibrium of Hydriodic Acid-
  9. 7-9 Toward Safe Hydrogen Production Utilizing High-Temperature Gas Cooled Reactor
    -Preventing the Hydrogen from Being Contaminated by Radioactive Material-
  1. 8-1 Toward MOX Reprocessing
    -Solvent Degradation and Its Effect on Pu Purification Cycle in Reprocessing Plant-
  2. 8-2 System for Stable Operation of Rotating Equipment
    -Monitoring Conditions by Shock Pulse Method-
  1. 9-1 Rational Approach to Decommissioning of Nuclear Facility
    -Developing a Fast Method for Evaluating Decommissioning Cost-
  2. 9-2 Preparing Reliable Waste Data Needed for Disposal
    -Development of Waste Management System Covering from Generation to Disposal-
  3. 9-3 Establishing Rational Clearance and Disposal System of Uranium-Bearing Waste
    -Understanding Natural Uranium Contribution to Natural Background Radiation-
  1. 10-1 Struggling with Background in Fissionable Nuclide Detection
    -Development of Hypersensitive Detection Method of a Trace Amount of Fissile Material-
  1. 11-1 DNA Double-Strand Breaks of Human Cancer Cells by Irradiation with Laser-Accelerated Protons
    -Toward Cancer Therapy by Laser-Driven Accelerators-
  2. 11-2 A Novel Compact and High Intensity Laser System
    -Development of Laser-Driven Particle Accelerator for Cancer Therapy-
  1. 12-1 Elucidation of Embrittlement of Iron by Sulfur and Phosphorous
    -The Mechanism of Grain Boundary Embrittlement Elucidated by First-Principle Calculations-
  2. 12-2 Cooperation of the World's Supercomputers for Nuclear Engineering Simulation
    -Development of Atomic Energy Grid Infrastructure AEGIS-
  3. 12-3 Search for the Superconducting Mechanism of Iron-Based Superconductors
    -SPring-8 X-ray Measurements Compared with First-Principles Calculations-
  4. 12-4 Supporting Evaluation of Tera- to Petabyte Scale Data
    -Proposal of Novel Data Analysis Method for Large Scale Simulation-
  1. 13-1 Continuous Monitoring of Nuclear Material
    -Advanced Algorithm of Process Monitoring-
  1. 14-1 Remote Nondestructive Examination of Steam Generator (SG) Heat Transfer Tubes
    -SG Heat Transfer Tubes Integrity Confirmation by Eddy Current Test, Visualization and Gas Leak Tests-
  2. 14-2 High Precision Calibration of Neutron Detectors in keV Region
    -Development of keV Region Mono-Energetic Neutron Calibration Fields Using an Accelerator-
  3. 14-3 New Reprocessing Method without Organic Reagent
    -Development of Uranium-Plutonium Cocrystallization Process-
  4. 14-4 For Reliability Improvement of LWR-MOX Fuels
    -Database of MOX Fuels Irradiated in "FUGEN" and "Halden"-
  5. 14-5 Toward a Higher Field Gradient
    -Development of Magnetic Alloy Core for the RF Cavity of J-PARC RCS-
  6. 14-6 Toward a Breakthrough in Hydrogen Storage Technology for a Hydrogen Society
    -Construction of Pulsed Neutron Total Diffractometer for Hydrogen Storage Materials-
  7. 14-7 Detecting Small Amount of Sodium Less than Salinity in Atmosphere
    -Sodium Leak Detector Using Laser Resonance Ionization Mass Spectrometry-
  8. 14-8 Innovative Method to Produce 99Mo for Medical Diagnosis without Uranium
    -Development of 99Mo Production Technique with Molybdate Solution-
  9. 14-9 Development of Technology for a Commercial High Temperature Gas-Cooled Reactor
    -Non-Destructive Inspection Method for Reactor Pressure Vessel-
  10. 14-10 Highly Sensitive Diagnosis of Asbestos Diseases Using Ion Microbeams
    -Identification of Asbestos Type in a Lung Tissue Cell-
  11. 14-11 Construction of Research Tunnels Deep Underground
    -Reduction of Water Inflow at the "Mizunami Underground Research Laboratory"-
  12. 14-12 Establishment of Traceability of Radon Measurements at JAEA
    -Standardization of Our Radon Measurement Techniques and Assuring Their Accuracy-
  13. 14-13 Search for the Migration of 129I on the Earth
    -Estimating Relative Sizes of 129I Original Sources-
  1. 1-1 Coolant Pipes Made Economically Competitive by Shortening
    - Development of High Chromium Steel for FBR Components Which Has Excellent High Temperature Strength, Toughness and Microstructural Stability -
  2. 1-2 Evaluation of the Structural Integrity of Reactor Vessels
    - Measurement of the Thermal Deformation near the Fluid Surface Using the Laser Speckle Method -
  3. 1-3 Determining Transfer / Damping of Temperature Fluctuation of Fluid to Structure
    - Evaluation of High Cycle Thermal Fatigue at Core Outlet in FBR -
  4. 1-4 Development of a Fuel Handling Method for a Compact Reactor Vessel
    - Fuel Handling Machine Bearing Endurance Test in Sodium Vapor -
  5. 1-5 Improved Analysis of Hypothetical Core Disruption Behavior in FBRs
    - 3-D Simulation of Complex Thermal-Hydraulic Phenomena under Very High Temperature -
  6. 1-6 Experimental Study on Molten Core Material Behavior
    - The EAGLE Project as a Collaborative Study with the Republic of Kazakhstan -
  7. 1-7 Analysis of Complex Phenomena upon Tube Failure in SG
    - Development of a Numerical Simulation Program Evaluating Sodium-Water Reaction Phenomena for Safety Assessment -
  8. 1-8 Development of Uranium Recovery System by Crystallization Technologies
    - R&D Status on Uranium Crystallization System for Future FBR Recycle System -
  9. 1-9 Toward Engineering Scale Minor Actinides Recovery
    - Development of Extraction Chromatography Techniques -
  10. 1-10 Toward Innovative MOX Fuel Production by Simplified Process
    - Developing a Unified Process Combining De-Nitration by Microwave Heating with Granulation -
  11. 1-11 Heat Removal during TRU Fuel Fabrication
    - Design Study of Heat Removal for TRU Fuel Fabrication System -
  1. 2-1 For the Utilization of Knowledge on Geological Disposal Technology
    - Detailed Design of Knowledge Management System -
  2. 2-2 Development of Buffer Material Database
    - Compilation of Characteristic Data of Buffer Material -
  3. 2-3 Estimation of Long-Term Metallic Corrosion Using Archaeological Sample
    - Application of Analogize Phenomena in Nature on Geological Isolation Research -
  4. 2-4 Realistic Application of Safety Assessment Methodology to Disposal Environments
    - Arrangement and Development of Basic Information Using FepMatrix Tools -
  5. 2-5 Development of Knowledge Base for HLW Disposal Technology
    - Technical Know-How and Analysis of Decision Criteria for Characterization of Geological Environment -
  6. 2-6 Development of Quality Assessment Method for Hydrochemical Data
    - Proposal of Methodology Based on Evidence Support Logic -
  7. 2-7 Study of Features of Active Faults Based on Measurement of Hydrogen Gas Emission from the Underground
    - Development and Application of Portable Hydrogen Gas Equipment -
  8. 2-8 Strategy for Long-Term Predictions for Geological Disposal R&D
    - Long Term Prediction of Groundwater Flow Changes Based on the Geological History -
  9. 2-9 Tracing Water Movement from Surface to Underground
    - Surface Hydrological Investigation at Horonobe Area, Hokkaido, Japan -
  10. 2-10 Tunneling Underground to Investigate Initial Stress Conditions
    - 3-D Initial Underground Stress Measurement by Hydraulic Fracturing -
  1. 3-1 Establishment of Long-Pulse Operation for "ITER" Burning Plasmas
    - Steady State Sustainment of High Confinement and High β Plasmas -
  2. 3-2 Intrinsic Rotation Due to Plasma Pressure Discovered
    - Toward the Understanding of High Pressure / Highly Self-Regulating Plasma -
  3. 3-3 Development of the Plasma Movie Database System for JT-60
    - Movie Data Handling Technology for Remote Experiment in the ITER-BA Project -
  4. 3-4 Achieving High Power in the JT-60U RF System
    - World Record for Gyrotron Oscillation (1.5MW,1s) -
  5. 3-5 World Record Achievement in Plasma Heating Device
    - Demonstrated High-Power and Steady-State Operation in Gyrotron toward ITER Construction -
  6. 3-6 Development of a Large Negative Ion Source
    - R&D for Maintenance Free Ion Source for Uniform Negative Ion Beam -
  7. 3-7 Demonstration of Final Installation to within 0.5mm of a 4-ton Blanket by Remote Handling
    - Improvement in a Robotic Positioning Control Scheme for ITER -
  8. 3-8 Materials Necessary for Stably Supplying Fuel Tritium to Fusion Reactors
    - Development of Tritium Breeding Materials Resistant to Reduction in Hydrogen -
  9. 3-9 Tritium Extraction Using a Fuel Cell
    - Tritium Recovery from Blanket Sweep Gas -
  10. 3-10 Torus Configuration and Maintenance Concept of Compact Fusion DEMO Reactor
    - Torus Configuration for High Operation Rate -
  1. 4-1 Making a Mirror Moving Nearly at the Speed of Light by Lasers
    - Demonstration of Light Reflection and Frequency-Upshifting by Electron Density
    Modulation in Plasmas -
  2. 4-2 Observation of a Key Hydrogen Atom in an Enzymatic Reaction
    - Neutron Structure Analysis of a Compound Modeling the Reaction Center of [NiFe]Hydrogenase -
  3. 4-3 Why Do Heavy Ions Have Great Effect on a Cell? Chemistry Elucidates the Reason
    - Quantitative Analysis of Reactive Species Which Induce DNA Damage -
  4. 4-4 Biodegradable Elastic Gel from Cellulose Derivatives
    - Combination of Radiation-Induced Crosslinking and Aggregation -
  5. 4-5 Medical Applications for the Laser-Driven Proton Beam
    - High Quality Beam Is Produced with High Conversion Efficiency -
  6. 4-6 Local Structure in a Material Shrinking with Heat
    - Broadening of Magneto-Volume Effect (Invar Effect) Caused by Local Lattice Distortion -
  7. 4-7 Observation of Electron Dynamics Utilizing Synchrotron Radiation X-ray
    - Charge Excitations in Ladder Cuprates by Resonant Inelastic X-ray Scattering -
  8. 4-8 Observation of Curious Long-Period Structures in Metal Hydride
    - A Clue to Understand the Hydrogen-Metal Interactions and Their Role -
  9. 4-9 A Breakthrough in Development of High-Temperature Polymer Electrolyte Membrane Fuel Cells
    - Successfully Making a Highly Heat-Resistant Proton-Conductive Aromatic Polymer Electrolyte Membrane -
  10. 4-10 Strain Measurement on Rebars in Reinforced Concrete
    - Application of Neutron Diffraction to Nondestructive Strain Measurement -
  11. 4-11 Compact and Low Noise Ultra-High Intensity Laser
    - Good Prospects for a Laser Driven Proton Accelerator for Cancer Therapy -
  12. 4-12 Mechanism for Biological Sensing of Ionizing Radiation
    - The Role of γ Subunit of G Protein in Caenorhabditis elegans -
  1. 5-1 To Learn from Operating Experience
    - Analysis of Primary Water Stress Corrosion Cracking Events at PWRs -
  2. 5-2 Simulation of MOX Fuel Irradiation Behavior for LWRs
    - Analysis of MOX Fuel Behavior in Halden Reactor by FEMAXI-6 Code -
  3. 5-3 Does Pellet Microstructure Change Affect Fuel Behavior during a RIA?
    - Fission Gas Release in High Burnup BWR Fuel under RIA Conditions -
  4. 5-4 Reactor Instruments to Prevent PWR Severe Accident
    - LSTF Test to Estimate Usefulness of Core Exit Thermocouple (CET) -
  5. 5-5 Measurement of Rapid Boiling and Vapor Void Behavior in Coolant among Fuel Rods
    - Toward Improved Prediction of Power Increase during RIAs -
  6. 5-6 Estimating Fracture Resistance of Reactor Pressure Vessel Steels
    - Estimating Toughness against Combination of Cleavage and Intergranular Fracture -
  7. 5-7 Taking Advantage of Spent Fuel Being Harder to Make Critical than Fresh Fuel
    - Acquisition of Verification Data for Burn Up Credit Analysis Methods -
  8. 5-8 Evaluating the Radioactivity Concentration of Radioactive Wastes below Which They Can Be Disposed
    - Dose Calculation to Derive the Upper Bound of Radioactivity Concentration in Disposal of Transuranium Wastes -
  9. 5-9 How Long Does a Repository Confine Radionuclides?
    - Modeling of Long-Term Alteration of Bentonite Buffer Material -
  1. 6-1 Chemical Characterization of Superheavy Elements
    - Fluoride Complexation of Element 104, Rutherfordium -
  2. 6-2 Heavy Fermion Superconductivity in Neptunium Compound
    - A New Material Advances Actinide Science -
  3. 6-3 Microscopic Investigations of Uranium and Trans-Uranium Oxides
    - Nuclear Magnetic Resonance Studies of the Electronic States -
  4. 6-4 Atomic Scale Observation of Metal Degradation
    - Development of a Positron Scanning Microscope -
  5. 6-5 Biological Effects of Clustered DNA Damage
    - Mutation Induction by DNA Lesions in Close Proximity -
  1. 7-1 Compilation of Reliable Nuclear Reaction Data
    - Development of Comprehensive Code for Nuclear Data Evaluation, CCONE -
  2. 7-2 Detailed Measurement of Boiling Flow
    - Monitoring 3D Change of Vapor / Water Distribution by Neutron Beam -
  3. 7-3 Demonstration of Excellent Thermal Properties of Minor Actinide Nitride Fuel
    - High-Quality Thermal Conductivity Data of MA Nitride Obtained from Small Samples -
  4. 7-4 New Approach for Testing Aging of Reactor Structural Materials
    - Study of Stress Corrosion Cracking (SCC) Mechanisms Using Electron Backscatter Diffraction (EBSD) in Mesoscale Analysis -
  5. 7-5 Advancement of Nuclear Medicine Dosimetry
    - Development of a Radionuclide Database Applicable to Microdosimetry in Subcellular Dimensions -
  6. 7-6 Selective Detection of Ultra-Fine Particles Containing Highly Enriched Uranium
    - Development of an Environmental Sample Analysis Method for IAEA Safeguards -
  7. 7-7 Improving Performance of Very High Temperature Reactor Fuel
    - Development of ZrC Coated Fuel Particle -
  8. 7-8 For Efficient H2 Production Using IS Process
    - Success in Measuring SO2 Pressurization Effect on the Bunsen Reaction -
  1. 8-1 Vitrification Melter Improvement
    - Development of Long-Life High Level Radioactive Liquid Waste (HLW) Vitrification Melter -
  2. 8-2 Developing to LLW Encapsulation Stage for Disposal
    - Future Planning of LLW Treatment at the Tokai Reprocessing Center -
  1. 9-1 Determination of 90Sr in Radioactive Waste
    - Development of Rapid and Simple Method for Evaluation of Radioactivity Inventories in Waste -
  1. 10-1 Development of Extra High Purity Stainless Steel (EHP Alloy) with High Corrosion Resistance in Severe Environment
    - Excellent Grain Boundary Corrosion Resistance of EHP Alloy under Boiling Nitric Acid -
  1. 11-1 Ion Acceleration from Near-Critical Density Plasma Produced by Lasers
    - Proposal of a Novel Ion Acceleration Method for Cancer Therapy -
  2. 11-2 One Optical Fiber Can Both Observe and Treat
    - Development of Extra-Fine Endoscope with Laser Radiation Function -
  1. 12-1 Computational Nuclear Power Plant Modeling and Structural Integrity Assessment
    - 3-D Vibration Simulator for Predicting Dynamic Behavior of Nuclear Power Plants -
  2. 12-2 Suppressing Bubble-Induced Material Damage by Gas Bubbles
    - Numerical Study of the Damage Suppression Effect of Bubble Injection -
  3. 12-3 Large-Scale Conformational Change of a Protein Elucidated by Computer Simulation
    - Molecular Mechanism of Cell Adhesion Protein Integrin -
  4. 12-4 Development of Steel Impurity Behavior Simulation Technology
    - Estimation of Impurities in Materials Based on Thermal Desorption Gas -
  1. 13-1 Nuclear Proliferation-Resistance and Safeguards for Future Nuclear Fuel Cycle
    - Study of the Evaluation Technique and Criteria of Nuclear Proliferation Resistance -
  1. 14-1 Evaluation of Radioactive Inventory in Nuclear Facility for Its Decommissioning
    - The Applicability of a Radioactive Inventory Evaluation Technique for "FUGEN" Verified -
  2. 14-2 Achieved Utilization of Short-Lived Radioactive Nuclei Beams
    - Development of Ion Sources for Radioactive Nuclei -
  3. 14-3 Study on Basic Properties for Establishment of a Fast Reactor Cycle System
    - Melting Temperatures and Phase Diagram of MOX Fuel -
  4. 14-4 Basic Knowledge on Treating Various Wastes Generated from Pyro-Reprocessing
    - Recovery of Actinides from Solid and Liquid Wastes -
  5. 14-5 Development of Damage Reduction Technique on Mercury Target for the Spallation Neutron Source
    - Visualization of the Bubble Formation Behavior in Mercury -
  6. 14-6 Measuring Displacement and Vibration of High Temperature and High Radiation Components Using Optical Fiber
    - Development of Fast Reactor Integrity Monitoring Technology -
  7. 14-7 Material Research for Transmutation of LLFP in a Fast Reactor
    - Irradiation Test of 11B4C as a Neutron Moderator -
  8. 14-8 Contribution to "ITER" by Technical Development of Post Irradiation Examinations
    - Remote-Handling Type Welding / Processing Techniques for Irradiated Materials -
  9. 14-9 Correlation between the Charge-State and Structure of Fragment Ions for Swift C3＋ Traversing a Thin Foil
    - Study on Interaction between a MeV Cluster Ion and a Matter -
  10. 14-10 Reduction of Water Inflow for Continuation of Deep Shaft Excavation
    - Development of Grouting Technology at the "Mizunami Underground Research Laboratory" -
  11. 14-11 To Accomplish Decommissioning of Uranium Enrichment Plant Safely and Economically
    - System Treatment Chemical Decontamination Technology by Fluoride Gas -
  12. 14-12 High Precision Measurement of Dissolved Organic Radiocarbon in Seawater
    - Development of a Pretreatment Method for AMS Measurement of Dissolved Organic Radiocarbon -
  1. 1-1 Handling Nuclear Data Accurately and Efficiently
    - Lattice Calculation Code Combining Ultra-Fine and Fine Group Calculations -
  2. 1-2 Ideal Fuel Cladding Materials for Fast Breeder Reactor Irradiated at Highest Temperature in the World
    - Microstructure Stability Evaluation of a Heavily Neutron-Irradiated Oxide Dispersion Strengthened Steel for Advanced Nuclear Reactors -
  3. 1-3 Toward Realization of Minor-Actinide Recycling in a Fast Reactor Cycle System
    - Development of Fabrication Technology of Advanced Oxide Fuel Containing Americium -
  4. 1-4 Accurate Temperature Analyses of FBRs in Low Flow Conditions
    - Heat Conduction and Heat Transfer between Subassemblies -
  5. 1-5 Experimental Study on Gas Entrainment Phenomena
    - Simultaneous Measurements of Flow Velocity Fields and Free Surface -
  6. 1-6 Achieving Efficient Fuel Handling
    - Study on the Fuel Handling System in a Commercial SFR -
  7. 1-7 Higher Accuracy in the Inspection Heat Exchanger Steam Generator Tubes of Nuclear Fast Reactors
    - Suppression of Sodium Adhesion ECT Signal Achieved by Numerical Simulations -
  8. 1-8 Investigation of Strength of Structural Material Using Controlled Temperature Fluctuation Loading
    - High Cycle Thermal Fatigue Tests in Sodium for Fast Reactor Design -
  9. 1-9 Analysis Shows that Reactor Trip Failure Probability Is Extremely Small
    - Aniticipated Transient without Scram ( ATWS) Frequency Evaluation of FBR "MONJU" -
  10. 1-10 Analysis of "MONJU" Thermal Transient Margin
    - Analysis of "MONJU" Thermal Transient Margin Based on Measured Plant Performance -
  11. 1-11 The Challenge of Maintaining Safety in an Extreme Environment
    - Development of an ISI Device for the Reactor Vessel of "MONJU" Fast Breeder Reactor -
  1. 2-1 Development of a Novel Knowledge Management System for Geological Disposal
    - Preliminary Design of Management Functions and Knowledge Base -
  2. 2-2 Characterization of Potential Changes in Geological and Disposal Environment Caused by Natural Phenomena
    - Development of Evaluation Procedure for HLW Disposal System Perturbation Scenarios -
  3. 2-3 Possibility of Superlong-Lifetime Container for Geological Disposal
    - Corrosion Behavior of Copper Overpack in Low Oxygen Concentration Environment -
  4. 2-4 Integration and Management of Mass Transfer Coefficient in Geological Environment
    -Development and Operation of Web Site for Diffusion Database (DDB) -
  5. 2-5 Finding Ancient Temperatures
    - Reconstruction of Past Climate Using Pollen Records from the Small Basin Deposit -
  6. 2-6 Underground Survey Using the Blasting Vibration During Shaft Excavation in the MIU-Site
    -Underground Imaging Technique Using a Geophysical Method -
  7. 2-7 Estimation of a Groundwater Flow by Minute Tilt
    - Estimation of Hydrogeological Structures by an Inverse Analysis of Tilt Data -
  8. 2-8 Estimation of Groundwater Quality from Specific Resistance Values
    - Improvement of Geostatistically-Based Estimation of Groundwater Quality -
  9. 2-9 Estimation of the 3D Distribution of Groundwater Chemistries
    - Hydrochemical Investigation in the Horonobe Underground Research Laboratory (URL) Project -
  10. 2-10 Inference of Hydrogeological Structure from Geological Observations
    - Development of Fracture Investigation Techniques for Sedimentary Rocks -
  1. 3-1 Accomplishment of the Conceptual Design of JT-60SA through Collaboration of Japan and Europe
    - JT-60SA Program for ITER-Supporting and ITER-Complementing Research -
  2. 3-2 The Search for the Plasma Rotation Needed for High Pressure Plasma
    - Finding the Minimum Plasma Rotation Suppressing Plasma Distortion -
  3. 3-3 Sharpening Plasma Shape Improves Pressure Limit
    - Stabilization of the Edge Localized Mode by Sharpening the Plasma Shape -
  4. 3-4 Suppression Mechanism of Turbulent Electron Heat Transport
    - Simulation Study of Microscopic Electron Turbulence in Tokamaks -
  5. 3-5 Development of Full Scale First Wall of Fusion Blanket
    - R&D of Diffusion Bonding for Fusion Blanket Manufacturing -
  6. 3-6 Developing a Method for Suppressing Irradiation Hardening of F82H by Heat Treatment Utilizing the Difference in the Hardening of Weld Joints
  7. 3-7 Measurement of Tritium Production Rate in Blanket with High Accuracy
    - Development of Measurement and Calculation Methods in Breeder Layer -
  8. 3-8 Material Allowing Stable Fuel Supply to Fusion Reactor
    - Development of Advanced Tritium Breeder Materials for Fusion Reactor -
  9. 3-9 Research on Interaction between Tritium and Metal
    - Pyramid-Like Blisters Formed by Hydrogen-Induced Local Superplasticity -
  10. 3-10 Neutron Shielding Resin Can Be Used in the High Temperature Environment of a Fusion Device
    - Development of Neutron Shielding Resin that Has High Heat Resistance and High Mechanical Strength -
  1. 4-1 Study Suggests the Existence of Ferroelectric Ice in Outer Space
    -A Neutron Diffraction Study of Ice XI-
  2. 4-2 Elucidation of Plant Growth Regulation by Ion Beams
    -The SMAP1 Gene Regulates Sensitivity to Plant Hormone-
  3. 4-3 Discovery of Phonons Causing Superconductivity in Diamonds
    - Looking for "Room Temperature-Superconductors" in Diamonds -
  4. 4-4 Discovery of Activation Enhancement Mechanism of DNA Repair Promoting Gene pprA
    - Role of Radiation Response Protein LexA2 -
  5. 4-5 Anomalous Spin Structure in Frustrated Magnet
    - Spin-Lattice Coupling Observed by a Neutron Scattering Technique -
  6. 4-6 Functional Diagnosis of Photosynthesis in a Leaf
    - Quantitative Kinetic Analysis of Photosynthetic Functions Using Positron Emitting Trace r Imaging System (PETIS) -
  7. 4-7 Photons Create New Heavy Elements in Supernovae
    - Photodisintegration Reaction Nucleosynthesis in Supernova Explosions -
  8. 4-8 Neutron Control by Magnetic Field
    - Development of Magnetic Optics to Highly Polarize and Focus Neutrons -
  9. 4-9 Promising Biodegradable Plastic for Industrial Applications
    - OFF-ON Control of Biodegradability in Polymer with Radiation and Chemical Modifications -
  10. 4-10 Direct Observation of Itinerant to Localized Transition of Heavy Electrons
    -Toward the Understanding of Heavy Fermion Materials -
  11. 4-11 Water Behavior in Concrete Observed Using Neutrons
    - Application to Deterioration Diagnostics of Concrete Structures -
  12. 4-12 Detection of Electric Circuit Malfunction Caused by Galactic Cosmic Rays
    - Mechanism of Transient Current Induced by High Energy Heavy Ions in Semiconductor Devices-
  13. 4-13 Clear Observation of Poorly Visible Objects Using High-Function X-rays
    - Generation of High-Brightness, High-Contrast X-rays by Terawatt Laser -
  1. 5-1 For Risk-Informed Safety Management in Nuclear Power Plants
    - Development of the Procedure for Uncertainty Analysis of Source Terms -
  2. 5-2 Evaluating the Influence of Hydrogen Absorption in the Clad on Fuel Failure
    -Failure of High Burnup Fuel in Reactivity Initiated Accident -
  3. 5-3 Degradation of Cladding Ductility Affected by Cooling History
    - Effect of Cooling History on Cladding Ductility under LOCA Conditions -
  4. 5-4 Boiling Heat Transfer Enhancement by Irradiation
    - Improvement of Critical Heat Flux by Radiation Induced Surface Activation -
  5. 5-5 Evaluating the Fracture Resistance of a Reactor Pressure Vessel under Pressurized Thermal Shock
    - Structural Reliability Evaluation of Aged Components in Nuclear Plants Based on Probabilistic Fracture Mechanics (PFM) -
  6. 5-6 Preparation for Nuclear Criticality Safety Evaluation of High-Burnup Fuel Cycle in the Near Future
    - Development of a High-Precision Evaluation Method for Nuclea r Criticality Safety of a 5 to 10% 235U-Enriched Uranium Fuel System -
  7. 5-7 Thermal Properties of Additional Material Used in MOX Fuel Fabrication Facility
    - Investigation of Data and Evaluation Model of Pyrolysis Properties of Zinc Stearate-
  8. 5-8 Mass Transport Retardation Studies under In Situ Conditions
    - Radionuclide Migration Experiments in a Rock Fracture at a Depth of 240m -
  9. 5-9 Evaluating the Radionuclide Concentrations at which Radioactive Materials Can Be Released from Regulatory Control
    - Clearance Level Calculation System Development -
  1. 6-1 Unusual Magnetic and Orbital Ordering in Np Compounds
    -Neutron Scattering Study of Actinides in JRR-3 -
  2. 6-2 Large Magnetoresistance Effect Found in Fullerene-Cobalt Thin Films
    -Organic Molecule Mediates Electron Spin -
  3. 6-3 A New Method for Material Synthesis under a Million G
    -Research into New Materials Utilizing "Mega-Gravitoronics" -
  4. 6-4 Artificial Enzymatic Synthesis of Cellulose
    - Elucidation of Self-Organization Mechanism of Reaction Products by Using Small-Angle Neutron Scattering Method -
  5. 6-5 Dependence of Yield of DNA Damage Refractory to Enzymatic Repair on Ionization & Excitation Density of Radiation
    -Exploring the Induction Mechanism of Clustered DNA Damage -
  1. 7-1 Experimental Investigation of Thermal Margin in Tight-Lattice Rod Bundle
    - Large-Scale Experiments under High Pressure Conditions -
  2. 7-2 Proposal for Future Waste Management
    - Reduction of the Repository Size for the High Level Wastes (HLW) by Introducing Partitioning and Transmutation (PT) Technology -
  3. 7-3 Attempts to Improve Radiolytic Stability of Amidic Extractants for the Separation of Actinides
    - Development of an Improved Extractant, Based on the Reaction Mechanism of Radiolysis -
  4. 7-4 Toward Clarification of Minor Actinides Behavior in Pyrochemical Processes
    - Preparation of Minor Actinide Chlorides without the Use of Corrosive Gases-
  5. 7-5 Radiation Dose Assessment for a Heavily Exposed Person without any Dosimeters
    - Dose Assessment by Measuring Activated Sodium in the Body -
  6. 7-6 Estimation of Quality and Quantity of DNA Damage Sites
    - New Method to Characterize DNA Damage Produced by Radiation -
  7. 7-7 Demonstration of Excellent Safety Characteristics of HTGR
    - Coolant Flow Reduction Test Using HTTR -
  8. 7-8 Outstanding Economic Efficiency of HTGR for Electricity Generation
    - Design Study on the HTGR with Gas Turbine -
  1. 8-1 Accurate Measurement of Plutonium Nitrate Solution
    - Accuracy & Reliability by Digital-Quartz Transducers Confirm ed by Comparison of Two Dens ities and by Applyin g Th em to Soluti on Mass Monitoring -
  2. 8-2 Contributions to Safeguards and Further Efficiency
    - Safeguards Improvement for the Tokai Reprocessing Plant -
  1. 9-1 Cutting Method for a Narrow Space with Little Heat Generation
    - Dismantling of the Core by the Abrasive Water Jet Cutting -
  2. 9-2 Measurement of Low Concentrations of Tritium in Concrete
    - Confirmation of Tritium Contaminant Clearance -
  1. 10-1 A Simulation Study of Intricate Crack Shapes
    -Large-Scale Simulation of Stress Corrosion Cracking Shape-
  2. 10-2 Detection of Nuclear Plant Structure Vibration
    - Vibration Analysis Technology for Simultaneous Evaluation of Different Wavelengths -
  3. 10-3 Measuring Twisting Modulus of DNA
    - Predicted Effects of Local Conformational Coupling and Ext ernal Restraints on the Torsio nal Properties of Single DNA Molecules -
  4. 10-4 Nanosecond Neutron Detection with Superconductor MgB2
    -Ultra-Fast Response Revealed by Simulations and Experiments -
  1. 11-1 Design of Safeguards System for an Advanced Nuclear Fuel-Cycle System
    -Development of Safeguards System Simulator -
  1. 12-1 Shortening the Modification Period in "MONJU"
    - Discussion of One-Loop Operation of Primary Heat Transport System in Fast Breeder Reactor "MONJU" and the Execution -
  2. 12-2 Heavy Ion Beams Lead the Way to Super Heavy Element Science
    - Development of Heavy Ion Injector in Terminal of Tandem Accelerator -
  3. 12-3 Toward a Better Understanding of High Burnup Fuel Behavior during Scenario Accidents in Nuclear Power Reactors
    - Design of Experimental Capsule for Irradiated Fuel Experiments -
  4. 12-4 Precise Estimation of the State of Oceans in the Past, Present and Future
    - Simulation of the Marine Diffusion of Radioactive Materials Using LAMER -
  5. 12-5 Study on Physical Properties of Fast Reactor Fuel for Future Commenricialization
    - Study on Thermal Conductivities of Uranium-Plutonium Mixed Oxide Fuels -
  6. 12-6 Measurement and Analysis of Deflection of Fuel Pins Irradiated in a Fast Reactor
    - Evaluation of Irradiation Effects Using the X-ray CT Technique -
  7. 12-7 Measuring Irradiation Time until Metal Specimen Rupture in Sodium Cooled Reactor
    - In-Pile Creep Rupture Experiment of Cladding Materials for Fast Reactor -
  8. 12-8 Upgrading of HTTR Burnup Characteristics Evaluation Method
    - Improvement of BP Burnup Characteristics -
  9. 12-9 Fabrication of a Micro-Scale Arc de Triomphe by MeV Focused Proton Beams
    - Development of a 3-Ds' Fine Fabrication Technique Using High Energy Submicron Ion Beams-
  10. 12-10 Battle Against Water Inflow: Five-year History of Mizunami Underground Research Laboratory
    - Development of Post-Grouting Technology for Deep Shaft -
  1. 1-1 Toward the Commercialization of Fast Reactor Fuel Cycle Systems
  2. 1-2 Fast Reactor System with Promise as Major Energy Source
    - Design Study of JAEA Sodium-Cooled Fast Reactor (JSFR) -
  3. 1-3 Smooth and Calm Flow in a Compact Reactor Vessel
    - Flow Optimization in a Compact Sodium Cooled Reactor -
  4. 1-4 Vibration Characteristics of Piping Excited by Turbulent Flows
    - Flow-Induced Vibration of Large Diameter Piping System under High Flow Velocity Condition -
  5. 1-5 Research and Development of Advanced Aqueous Reprocessing and Simplified Pelletizing Fuel Fabrication
    - Fuel Recycling System (Reprocessing and Fuel Fabrication) for the Next Generation -
  6. 1-6 Solvent Extraction of Actinide Elements in New Extraction System for TRU Recovery (NEXT)
    - Development of Advanced Reactor Fuel Reprocessing -
  7. 1-7 Establishment of a Remote Fabrication Technique Making Fast Reactor Fuel from Excess Minor Actinide
    - Development of Fabrication Technique for MOX Fuels Containing Americium -
  8. 1-8 Search for the Way to Nuclear Power Sustainability
    - Fast Reactor Cycle Deployment Scenario Analysis -
  9. 1-9 Finding Promising Fast Reactor Cycle Concepts from Multiple Viewpoints
    - Multidimensional Evaluation of Fast Reactor Cycle Systems -
  10. 1-10 Probabilistic Safety Assessment Study of Fast Reactor Cycle
    - Development of World's First Safety Evaluation Method for the Entire Fuel Cycle -
  11. 1-11 System Start Up Test of the Prototype Fast Breeder Reactor MONJU
    - From the Achieved Test Results (Criticality Test to Power Up Test (40% Power)) -
  12. 1-12 Prediction of Unplanned MONJU Shutdown Frequency
    -Reactor Trip Frequency Prediction Using Fault Tree Analysis Method -
  13. 1-13 An Advanced Transport Cross-Section Collapsing Method for Three Dimensional Transport Code Was Developed
    - MONJU Core Neutronics Analysis Method Upgrading Research -
  14. 1-14 Personal Computer Plant Simulation in 1/1000 Real Time
    - Validation of Versatile Plant Simulation Code -
  15. 1-15 Study of Fast Breeder Reactor Safety with Laser
    - Fuel Failure Detection System by means of Laser Resonance Ionization Mass Spectrometry -
  16. 1-16 Development of Multi-Functional Reprocessing and Utilization of Separated Elements
    - Establishment of Advanced Separation Process Using Pyridine Resin -
  17. 1-17 Viewing Inside an Irradiated Fuel Assembly
    - Development of a Non-Destructive Post-Irradiation Examination Technique Using High-Energy X-ray Computer Tomography -
  1. 2-1 R&D Supporting the Technology and Reliability of Geological Disposal in Japan
  2. 2-2 Development of a Novel Knowledge Management System for Geological Disposal
    - Fundamental Concepts and Implementation Plan -
  3. 2-3 Development of Reliable Databases for Safety Assessment of High-Level Radioactive Waste Disposal System
    - Database Development for Radionuclide Migration Analysis -
  4. 2-4 Development of Low Alkaline Cement
    - Study on Workability of Low Alkaline Shotcrete -
  5. 2-5 Prediction of Long Term Changes at Barriers
    - Development of a Coupled Thermo-, Hydro-, Mechanical, and Chemical Model -
  6. 2-6 Study Plan for Performance Assessment of High-Level Radioactive Waste Geological Disposal (5-year Plan)
    - For Development of Technical Basis for System Performance Assessment in Implementation Phase -
  7. 2-7 Imaging Crustal Magma beneath an Active Volcano and the Generation of High Temperature Hot Springs in a Non-Volcanic Region
    - Magnetotelluric Modeling in Naruko Volcanic Region and Kii Peninsula -
  8. 2-8 Paleo-Hydrochemical Conditions Recorded in Calcite
    - Long-Term Stability of Geochemical Environment Deep Underground -
  9. 2-9 Study of Environmental Disturbance by an Underground Facility
    - Estimate of Hydrochemical Disturbance Resulting from Drift Excavation -
  10. 2-10 Magnetotelluric Survey of 3-Dimensional Distribution and Hydrogeological Properties of Faults
    - Development of Techniques for Investigating Geological Environment -
  11. 2-11 Saline Concentration Indicates Groundwater Flow
    - Relationship between Saline Concentration Distribution and Groundwater Flow in Sedimentary Rock -
  12. 2-12 Detecting the Stress Distribution of Deep Sedimentary Rock in Northernmost Japan
    - Construction of a Dynamic Model of Tertiary Siliceous Rock Based on Laboratory and In-Situ Measurement -
  13. 2-13 Results of Transuranium (TRU) Waste Disposal Studies
    - From the 2nd TRU Progress Report -
  1. 3-1 For Practical Use of Fusion Energy
  2. 3-2 Prospects of Reduced Cost of Electricity from Fusion Power Plants
    - Energy-Saving Operation for Fusion Power Plants in JT-60 -
  3. 3-3 Insulator Generated in High-Temperature Plasma
    - Anomaly of Current Profiles Observed in JT-60 -
  4. 3-4 Mechanism of Confinement Improvement in Tokamak Plasmas
    - Control of Turbulent Transport by Zonal Flow Modification -
  5. 3-5 Image of Radiation from 1/4 of a Donut Plasma
    - Development of an Infrared Imaging Bolometer in JT-60U -
  6. 3-6 Concept for a Reduced Cost Fusion Reactor
    - Compact Reactor Allowing Early Realization of Fusion Power -
  7. 3-7 Achievement of 1000 s High Power Radio-Frequency
    - Establishment of Gyrotron Technology for Stable & Steady State Operation -
  8. 3-8 Reduction of the Heat Load on Acceleration Grids in the Negative Ion Based Neutral Beam Injector
    - A Step Toward Long Pulse Beam Injection -
  9. 3-9 Uniform Production of H- Ions in a Large Ion Source
    - Technology for High Power Neutral Beam Injection System -
  10. 3-10 Pioneering Material for ITER Superconducting Wire
    - Success in Mass Production of High Performance Nb3Sn Strands -
  11. 3-11 New Stainless Steel for High Performance Superconducting Coil
    - Development of ITER Central Solenoid Conductor Conduit Material -
  12. 3-12 Compact Fusion Reactor Using Advanced Shield Materials
    - Application of Hydrogen-Rich Hydride to the Shield of Fusion Reactor -
  13. 3-13 Measurement of Hydrogen Depth Profile Using Fast Neutrons
    - Materials Analysis with Deuterium and Tritium Fusion Neutrons -
  14. 3-14 Accelerator Development for International Fusion Materials Irradiation Facility(IFMIF)
    - A Key to Strong, Steady Beam Acceleration is Precise Radio-Frequency Property Adjustment -
  15. 3-15 R&D of New Detritiation System Using Bacteria
    - Incubating Tritium Oxidizing Bacteria from the Forest Soil -
  1. 4-1 Pioneering R&D of Quantum Beam Technology
  2. 4-2 Hydrogen Separation by Nano Hole Ceramics
    - Development of Heat and Corrosion Resistant Hydrogen Separation Silicon Carbide Based Membrane -
  3. 4-3 Development of New Monitoring Technology for the Utilization of Hydrogen as a Clean Energy Source
    - Optical Hydrogen Sensors Using Gasochromic Phenomenon -
  4. 4-4 Novel Technique for Characterization of Chemical Modification of Internal Surface of Nano-Pores
    - Fabrication of Functional Polymer Materials Using Ion Beams -
  5. 4-5 Confirming Cost Estimations of Uranium Collection from Seawater
    - Assessing High Function Metal Collectors for Seawater Uranium -
  6. 4-6 Elucidation of the Gene Activation Mechanism and Application to Visualization of DNA Strand Breaks
    - DNA Repair Promoting Protein PprA -
  7. 4-7 Plants Become More Tolerant to Ultraviolet (UV) Light by Increasing Nuclear DNA Content
    - Discovery of Novel UV Resistance Mechanism in Plants -
  8. 4-8 Elucidation of the Mechanism of Granulocytopenia Drug
    - Tertiary Structure Analysis of Human GCSF with its Receptor -
  9. 4-9 Observation of Electronic Structure Utilizing Synchrotron Radiation X-rays
    - Electronic Excitations by Resonant Inelastic X-ray Scattering -
  10. 4-10 Residual Stress Measurement of Internal Materials Using Synchrotron Radiation
    - Stress Analysis Technique with a New Strain Scanning Method -
  11. 4-11 Synchrotron X-rays Revealing Crystal Growth Front at the Atomic Level
    - Monitor for Gallium Arsenide Growth Using Synchrotron X-rays -
  12. 4-12 Attempt to Control Quantum Dot Size
    - Measurement of the Number of Atoms in a Nanocluster -
  13. 4-13 Toward a Practical Small Proton Cancer Therapy Machine
    - Discovery of Optimum Conditions for Laser Driven Proton Acceleration -
  14. 4-14 Quasi-Monoenergetic Electron Beam Generation by Using an Intense Laser Pulse
    - High Quality Electron Beam Source by Laser Acceleration -
  15. 4-15 Demonstration of Ultrafast Selective Excitation with Quantum Interference
    - Toward a New Method of Isotope Separation -
  16. 4-16 R&D of High Power Neutron Sources
    - Micropit Formation by Pressure Wave in Mercury Target -
  17. 4-17 Development of High Performance Neutron Supermirror
    - For Higher Fluxes at the Spallation Neutron Source of J-PARC -
  1. 5-1 Role and Scope of Nuclear Safety Research
  2. 5-2 Toward Risk-Informed Safety Management of Nuclear Fuel Facilities
    - Development of Probabilistic Safety Assessment Procedures for MOX Fuel Fabrication Facilities -
  3. 5-3 Safety Evaluation of Long-Term Irradiated Light Water Reactor Fuels
    - High Burnup Fuel Behavior in a Reactivity Initiated Accident -
  4. 5-4 Is Safety Maintained in Loss-Of-Coolant Accident even with Long-Term Used Fuel?
    - Evaluation of Light Water Reactor Fuel Behavior under LOCA Conditions -
  5. 5-5 Analysis of Rod Failure Mechanism in Accident Conditions
    - Development of the RANNS Code -
  6. 5-6 Verified Effectiveness of Pressurized Water Reactor Severe Accident Management
    - Even When Break Is at the Worst Location in PWR Primary Coolant System -
  7. 5-7 Evaluating the Risk of Steam Explosions
    - Simulation of Fuel-Coolant Interactions -
  8. 5-8 Containment Protection Using Natural Force
    -Experiment Using Horizontal Heat Exchanger for Passive Containment Cooling System (PCCS) -
  9. 5-9 Evaluating the Failure Probability of Aged Piping under Seismic Motion
    - Structural Reliability Evaluation of Aged Components in Nuclear Power Plants Based on Probabilistic Fracture Mechanics (PFM) -
  10. 5-10 Safe and Efficient Criticality Control of Spent Fuels
    - Development of Calculation Code and Database for Burnup Credit -
  11. 5-11 Durability of Vitrified Concrete and Incinerator Ash
    - Checking for Dissolution of Vitrified Radioactive Waste Form in Disposal Environments -
  1. 6-1 Advanced Basic Research to Create the Future
  2. 6-2 Investigation of Stability of the Nucleus through Deformed States
    - Observation of Rotational States in the Neutron-Rich250Cm Nucleus -
  3. 6-3 How Far Does the Area of Superheavy Elements Extend?
    - Decay Modes of Heavy and Superheavy Nuclei -
  4. 6-4 First Identification of Quantum States in Superheavy Nuclei
    - Nuclear Structure Studies for Superheavy Nuclei through α-γ Spectroscopy -
  5. 6-5 Investigation of New Plutonium-Based Superconductor
    - Identification of Exotic Superconducting State by Nuclear Magnetic Resonance -
  6. 6-6 Magnetism of Plutonium-Metal Probed by μSR
    - An Unsolved Problem of Solid State Physics -
  7. 6-7 New Surface Structures Found with Bright Positron Beam
    - Surface Dynamics Revealed by Positron Total Reflection -
  8. 6-8 Mineralization of Uranium by Yeast
    - Elucidation of Mechanism of Uranium Mineralization by Microorganism -
  1. 7-1 Formation of Basis for R&D on Nuclear Energy, and Creation of Innovative Nuclear Energy Utilization Technology
  2. 7-2 Predicted Two-Phase Flow Behavior in Nuclear Reactors
    - Development of Detailed Two-Phase Flow Simulation Method -
  3. 7-3 Development of Organic Material for the Recovery of Transuranium Elements
    - The Novel Strong Ligand, Diglycolamide, for Total Recovery of Minor Actinides -
  4. 7-4 Preparation of Nitride Fuel in the Pyrochemical Reprocessing of Spent Fuel
    - Technological Development of Renitridation of Plutonium Recovered in Liquid Cathode -
  5. 7-5 Investigations of Irradiation Assisted Stress Corrosion Cracking (IASCC) Behavior for Reactor Materials
    - Achievement of In-Pile SCC Tests at JMTR -
  6. 7-6 Distribution Maps of Anthropogenic Radionuclides in the Japan Sea
    - Transport Processes of Radionuclides in the Japan Sea -
  7. 7-7 DARWIN
    - Dose Monitoring System Applicable to Various Radiations with Wide Energy Ranges -
  8. 7-8 Towards Treatment of Toxic Materials and Utilization of Radioactive Wastes
    - A Novel Method for Non-Toxic Treatment of Cr (VI) Wastes by Using Ionizing Radiation -
  9. 7-9 Towards Reducing Tritium Concentration in the Hydrogen Produced by Very High Temperature Reactors
    - Permeability of Hydrogen of Operating Reactor Measured for the First Time -
  10. 7-10 Progress in Nuclear Production of Hydrogen
    - Successful Production of Ceramic Sulfuric Acid Decomposer Prototype -
  1. 8-1 To Establish the Nuclear Fuel Cycle
    - Promoting Light Water Reactor (LWR) Nuclear Fuel Cycle Technological Development and Technical Co-Operation with Private Industry -
  2. 8-2 Characteristics of HLW Generated from Future Cycles
    - Perspectives on Application and Flexibility of Current Vitrification Technology for High Level Wastes (HLW) Generated from Future Fuel Cycles -
  3. 8-3 Study on the Denitration Process of Uranyl Nitrate Solution by Microwave Heating
    - Uranium Powder Production Process from Uranium Nitrate Solution -
  4. 8-4 Approach towards an Explication of the Corrosion Mechanism for Reprocessing Plant Instruments
    - Investigation of Causes of a Failed Steam Jet and Improving the Jet Design -
  5. 8-5 Development of Acidity Analysis without Reagents
    - Determination of Acidity in Nitric Acid Solutions Containing Pu and U at High Concentration by Electric Conductivity Measurement -
  1. 9-1 Nuclear Facility Decommissioning and Radioactive Waste Management
  2. 9-2 Simplification of Radiochemical Analysis Method for Safe Disposal of Radioactive Wastes
    - Effective Pretreatment for Radiochemical Analysis of Solidified Products with Microwave Heating Device-
  3. 9-3 Development of Decommissioning Engineering Support System (DEXUS)
    - Database and Dismantling Work Simulation System (VRdose) -
  1. 10-1 Promoting Innovation in Nuclear Energy with Computational Science
  2. 10-2 Exploration of Room Temperature Superconductivity through the Super Strong-Coupling Superfluid Quantized Vortex
    - A World of the Room Temperature Superconductivity Revealed by Quantized Vortices in Atomic Fermi Gas -
  3. 10-3 Assembly Structure Analysis of Extra Large-Scale Nuclear Plants
    - Grid-Based Extra Large-Scale Structural Analysis by a Part Oriented Approach -
  4. 10-4 Attempt to Overcome Quantum Many-Body Problem Limits with the Earth Simulator
    - Fast and Accurate Diagonalization of Enormous Matrix -
  5. 10-5 Why Water Can't Be Heated or Cooled Easily?
    - A Molecular Theory for the Specific Heat of Water -
  6. 10-6 Phase Property and Interaction Force of Pulsating Multiple Bubbles
    - Existence of an Unknown Characteristic Frequency Is Confirmed -
  7. 10-7 Various Usage of Metal Ions by Living Organisms
    - Prediction of Copper-Binding Proteins from Genome Sequences -
  8. 10-8 A Computational Method to Predict RNA Interface Sites on Protein
    - Research in Structural Bioinformatics -
  9. 10-9 Bubbles' Hidden Complexity
    - An Anomalous Phenomenon "Avoided Crossing" Has Been Found in Bubbles Interacting through Sound -
  1. 11-1 Direction of Scientific & Technical Development for Nuclear Nonproliferation
  2. 11-2 Exchange of Remote Monitoring Information for Transparent Nuclear Materials Utilization
    - Development of Remote Monitoring Technology for Nuclear Nonproliferation and Transparency -
  3. 11-3 How Can Weapons Plutonium Be Disposed of Safely and Effectively?
    - Research into Russian Surplus Weapons Plutonium Disposition -
  4. 11-4 Development of Analysis Method for Burnup and Generated Amount of Plutonium by Measurement of Dissolver Off-Gas at Reprocessing Facility
    - Evaluation Technology for Burnup and Generated Amount of Plutonium by Measurement of Xenon Isotopic Ratio -
  5. 11-5 Determination of Small Amounts of Plutonium in Highly Radioactive Liquid Waste
    - Development of a Simple Inspection Technique Using Spectrophotometry -
  1. 12-1 "Representative Point Calibration Method" for Efficiency Calibration of Radioactivity Measuring Instrument
    - Development of a Method for Determining Radioactivity in Samples of Various Shapes -
  2. 12-2 Development of Human Dosimetry Technique in Criticality Accidents by Combined Use of Small Dosimeters
    - Speedy and Accurate Notification of Dose Information for Radiation Emergency Medicine -
  3. 12-3 Contribution to Leading-Edge Medical Technology
    - Development of a Supporting System for Boron Neutron Capture Therapy -
  4. 12-4 More Precise Measurement of Fuel Temperature Distribution in HTTR
    - Development of HTTR Fuel Temperature Estimation Model -
  5. 12-5 Remote Handling Techniques for Irradiation Assisted Stress Corrosion Cracking (IASCC) Study
    - Assembling of Irradiated Specimens in Capsule -
  6. 12-6 Neutronic Evaluation for Irradiation Tests of JMTR
    - Accurate Evaluation of Tritium Production -
  7. 12-7 Cyclotron Beam Stabilization Technique
    - Improvement of Beam Quality for Microscopic Irradiation -
  8. 12-8 Construction of an Underground Research Laboratory Fully Underway
    - Research and Development of Geological Disposal Technology -
  9. 12-9 High Sensitivity Measurement of Iodine-129 by Accelerator Mass Spectrometry (AMS)
    - New Technique Has Shorter Processing Time, Higher Precision and Higher Sensitivity than Neutron Activation Analysis (NAA) -