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) -