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Published by Japan Atomic Energy Agency

Published in January 2018

ONLINE ISSN:2188-1456

PRINT ISSN:2423-9992

 

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  • 1 Research and Development Related to the Accident at TEPCO’s Fukushima Daiichi NPS
  1. 1 Research and Development Related to the Accident at TEPCO’s Fukushima Daiichi NPS
  2. 1-1 Observation of Core Melting and Relocation Behavior under Severe-Accident Conditions
    －Plasma-Heating Tests with a Simulated Fuel Assembly－
  3. 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－
  4. 1-3 Toward Estimating Characteristics of Radioactive Material Released in Severe Accidents
    －Experimental and Analytical Technologies for Evaluating Fission Product Chemistry in a Reactor－
  5. 1-4 Thermodynamic Estimation of Fuel Debris Characteristics
    －Thermodynamic Evaluation of High-Temperature-Reaction Products between Molten Core and Concrete－
  6. 1-5 Can Fuel Debris be Retrieved without Water?
    －Development of a Numerical-Simulation Method for Air Cooling of Fuel Debris－
  7. 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－
  8. 1-7 Estimation of the Amount of Radioactivity in Water-Treatment Waste
    －Calculation of Radionuclide Concentration in Contaminated Water－
  9. 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－
  10. 1-9 Study of the Contamination State inside the Reactor Building
    －Detailed Radiochemical Analysis to Accelerate Disposal of Waste－
  11. 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－
  12. 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－
  13. 1-12 Fiber Detector for Monitoring of Contaminated Water
    －Demonstration Experiment at the TEPCO’s Fukushima Daiichi NPS－
  14. 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?－
  15. 1-14 How Long Does Radiocesium Remain in Forest-Surface Litter?
    －Radiocesium Transfer from Litter to Mineral Soil in Two Forest Types－
  16. 1-15 Mechanism of Vertical Migration of Radiocesium into Soils
    －Effect of Sorption Kinetics upon Vertical Migration of Radiocesium into Soils－
  17. 1-16 Redeposition Mechanism of Radiocesium on River Flood Plains
    －Heterogeneous Distribution of Radiocesium Depending on Weather, Topography and Vegetation－
  18. 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－
  19. 1-18 Reproduction of the Soil using Salt
    －Synchrotron X-rays Reveal the Mechanism of Cesium Removal from Soil－
  20. 1-19 Observation of Atomic-Scale Edge Structure via Supercomputers
    －Towards an Understanding of the High Cesium Affinity of Clay Minerals－
  21. 1-20 Prevention of Radioactive Cesium Accumulation in Shiitake Mushrooms Cultured with Contaminated Wood Logs
    －Reduction of Cesium Absorption using Minerals－
  • 2 Nuclear Safety Research
  • 3 Advanced Scientific Research
  • 4 Nuclear Science and Engineering Research
  1. 4 Nuclear Science and Engineering Research
  2. 4-1 Prevention of Severe-Accident Progression by Delaying Core Overheating and Melting
    －Development of FEMAXI-ATF Code for Accident-Tolerant Fuel-Behavior Analysis－
  3. 4-2 Efficient Partition of Nuclides in High-Level Waste
    －High-Efficiency Separation of Americium and Curium－
  4. 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－
  5. 4-4 Real-Time Measurement of Heavy-Liquid-Metal Flow under a Severe Environment
    －Development of an Ultrasonic Flowmeter for a Lead-Bismuth Target－
  6. 4-5 Interface of Nuclear Data and Transport Codes
    －Development of Nuclear Data Processing System FRENDY－
  7. 4-6 Research on the Material-Degradation Behavior by Radiolytic-Hydrogen Absorption
    －Hydrogen-Absorption Behavior on Zirconium under γ-ray Irradiation－
  8. 4-7 Predicting Mechanical Properties of Alloys
    －Computational Approach for Modeling the Strengthening/Softening Mechanism－
  9. 4-8 Quantitation of the Difficult-to-Measure Nuclide Palladium-107
    －Measurement of Palladium Obtained by Laser Irradiation of Spent Nuclear Fuel－
  10. 4-9 Forecast of Radionuclide Dispersion in the Ocean
    －Development of an Emergency-Assessment System for Marine-Environmental Radioactivity－
  11. 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－
  • 5 Applied Neutron and Synchrotron-Radiation Research and Development
  • 6 HTGR Hydrogen and Heat Application Research
  • 7 Research and Development of Fast Reactors
  • 8 Research and Development on Fuel Reprocessing, Decommissioning, and Radioactive Waste Management
  1. 8 Research and Development on Fuel Reprocessing, Decommissioning, and Radioactive Waste Management
  2. 8-1 Quantifying the Radioactivity of Waste Products
    －Accuracy Improvement of a Quantitative Method Focused on Scattering γ-rays－
  3. 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－
  4. 8-3 Understanding the Self-Sealing Function of the Underground Environment
    －Study of the Long-Term Behavior of Hydrogeological Structures Related to Faulting－
  5. 8-4 Micropores Retarding Mass Transport in Granitic Rock
    －Visualization and Observation of Matrix-Diffusion Pathways－
  6. 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)－
  7. 8-6 Investigation of the Fault Distribution in Sedimentary Rocks
    －Relationship between Faults Oriented Parallel and Oblique to Bedding in Neogene Massive Siliceous Mudstones－
  8. 8-7 Dating of Minerals in Rocks
    －Technical Development of a Rapid CHIME Dating Procedure－
  9. 8-8 Mechanistic Modeling of Nuclide Migration in Rock
    －Clay-Based Modeling Approaches for Diffusion and Sorption in Mudstone－
  10. 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－
  11. 8-10 Improvement of the Uncertainty and Rapidity of the Measurement Technique for a Plutonium Nitrate Solution Sample
    －Improvement of Neutron Nondestructive Assay－
  12. 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－
  • 9 Computational Science and E-Systems Research
  • 10 Development of Science & Technology for Nuclear Nonproliferation