Top Page>JAEA R&D Review 2007


Published by Japan Atomic Energy Agency

ONLINE ISSN 2188-1456

CD-ROM ISSN 2188-1421


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  • 1 Research and Development of Advanced Nuclear System
  1. 1 Research and Development of Advanced Nuclear System
  2. 1-1 Handling Nuclear Data Accurately and Efficiently
    - Lattice Calculation Code Combining Ultra-Fine and Fine Group Calculations -
  3. 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 -
  4. 1-3 Toward Realization of Minor-Actinide Recycling in a Fast Reactor Cycle System
    - Development of Fabrication Technology of Advanced Oxide Fuel Containing Americium -
  5. 1-4 Accurate Temperature Analyses of FBRs in Low Flow Conditions
    - Heat Conduction and Heat Transfer between Subassemblies -
  6. 1-5 Experimental Study on Gas Entrainment Phenomena
    - Simultaneous Measurements of Flow Velocity Fields and Free Surface -
  7. 1-6 Achieving Efficient Fuel Handling
    - Study on the Fuel Handling System in a Commercial SFR -
  8. 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 -
  9. 1-8 Investigation of Strength of Structural Material Using Controlled Temperature Fluctuation Loading
    - High Cycle Thermal Fatigue Tests in Sodium for Fast Reactor Design -
  10. 1-9 Analysis Shows that Reactor Trip Failure Probability Is Extremely Small
    - Aniticipated Transient without Scram ( ATWS) Frequency Evaluation of FBR "MONJU" -
  11. 1-10 Analysis of "MONJU" Thermal Transient Margin
    - Analysis of "MONJU" Thermal Transient Margin Based on Measured Plant Performance -
  12. 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 -
  • 2 Research and Development on Geological Disposal of High-Level Radioactive Waste
  1. 2 Research and Development on Geological Disposal of High-Level Radioactive Waste
  2. 2-1 Development of a Novel Knowledge Management System for Geological Disposal
    - Preliminary Design of Management Functions and Knowledge Base -
  3. 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 -
  4. 2-3 Possibility of Superlong-Lifetime Container for Geological Disposal
    - Corrosion Behavior of Copper Overpack in Low Oxygen Concentration Environment -
  5. 2-4 Integration and Management of Mass Transfer Coefficient in Geological Environment
    -Development and Operation of Web Site for Diffusion Database (DDB) -
  6. 2-5 Finding Ancient Temperatures
    - Reconstruction of Past Climate Using Pollen Records from the Small Basin Deposit -
  7. 2-6 Underground Survey Using the Blasting Vibration During Shaft Excavation in the MIU-Site
    -Underground Imaging Technique Using a Geophysical Method -
  8. 2-7 Estimation of a Groundwater Flow by Minute Tilt
    - Estimation of Hydrogeological Structures by an Inverse Analysis of Tilt Data -
  9. 2-8 Estimation of Groundwater Quality from Specific Resistance Values
    - Improvement of Geostatistically-Based Estimation of Groundwater Quality -
  10. 2-9 Estimation of the 3D Distribution of Groundwater Chemistries
    - Hydrochemical Investigation in the Horonobe Underground Research Laboratory (URL) Project -
  11. 2-10 Inference of Hydrogeological Structure from Geological Observations
    - Development of Fracture Investigation Techniques for Sedimentary Rocks -
  • 3 Nuclear Fusion Research and Development
  • 4 Quantum Beam Science Research
  1. 4 Quantum Beam Science Research
  2. 4-1 Study Suggests the Existence of Ferroelectric Ice in Outer Space
    -A Neutron Diffraction Study of Ice XI-
  3. 4-2 Elucidation of Plant Growth Regulation by Ion Beams
    -The SMAP1 Gene Regulates Sensitivity to Plant Hormone-
  4. 4-3 Discovery of Phonons Causing Superconductivity in Diamonds
    - Looking for "Room Temperature-Superconductors" in Diamonds -
  5. 4-4 Discovery of Activation Enhancement Mechanism of DNA Repair Promoting Gene pprA
    - Role of Radiation Response Protein LexA2 -
  6. 4-5 Anomalous Spin Structure in Frustrated Magnet
    - Spin-Lattice Coupling Observed by a Neutron Scattering Technique -
  7. 4-6 Functional Diagnosis of Photosynthesis in a Leaf
    - Quantitative Kinetic Analysis of Photosynthetic Functions Using Positron Emitting Trace r Imaging System (PETIS) -
  8. 4-7 Photons Create New Heavy Elements in Supernovae
    - Photodisintegration Reaction Nucleosynthesis in Supernova Explosions -
  9. 4-8 Neutron Control by Magnetic Field
    - Development of Magnetic Optics to Highly Polarize and Focus Neutrons -
  10. 4-9 Promising Biodegradable Plastic for Industrial Applications
    - OFF-ON Control of Biodegradability in Polymer with Radiation and Chemical Modifications -
  11. 4-10 Direct Observation of Itinerant to Localized Transition of Heavy Electrons
    -Toward the Understanding of Heavy Fermion Materials -
  12. 4-11 Water Behavior in Concrete Observed Using Neutrons
    - Application to Deterioration Diagnostics of Concrete Structures -
  13. 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-
  14. 4-13 Clear Observation of Poorly Visible Objects Using High-Function X-rays
    - Generation of High-Brightness, High-Contrast X-rays by Terawatt Laser -
  • 5 Nuclear Safety Research
  1. 5 Nuclear Safety Research
  2. 5-1 For Risk-Informed Safety Management in Nuclear Power Plants
    - Development of the Procedure for Uncertainty Analysis of Source Terms -
  3. 5-2 Evaluating the Influence of Hydrogen Absorption in the Clad on Fuel Failure
    -Failure of High Burnup Fuel in Reactivity Initiated Accident -
  4. 5-3 Degradation of Cladding Ductility Affected by Cooling History
    - Effect of Cooling History on Cladding Ductility under LOCA Conditions -
  5. 5-4 Boiling Heat Transfer Enhancement by Irradiation
    - Improvement of Critical Heat Flux by Radiation Induced Surface Activation -
  6. 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) -
  7. 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 -
  8. 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-
  9. 5-8 Mass Transport Retardation Studies under In Situ Conditions
    - Radionuclide Migration Experiments in a Rock Fracture at a Depth of 240m -
  10. 5-9 Evaluating the Radionuclide Concentrations at which Radioactive Materials Can Be Released from Regulatory Control
    - Clearance Level Calculation System Development -
  • 6 Advanced Science Research
  • 7 Nuclear Science and Engineering Research
  • 8 Nuclear Fuel Cycle Technological Development
  • 9 Development of Technology on Nuclear Cycle Backend
  • 10 Computational Science and E-Systems Research
  • 11 Scientific & Technical Developments for Nuclear Nonproliferation
  • 12 Development of Experimental Techniques/Facilities at JAEA R&D Centers
  1. 12 Development of Experimental Techniques/Facilities at JAEA R&D Centers
  2. 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 -
  3. 12-2 Heavy Ion Beams Lead the Way to Super Heavy Element Science
    - Development of Heavy Ion Injector in Terminal of Tandem Accelerator -
  4. 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 -
  5. 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 -
  6. 12-5 Study on Physical Properties of Fast Reactor Fuel for Future Commenricialization
    - Study on Thermal Conductivities of Uranium-Plutonium Mixed Oxide Fuels -
  7. 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 -
  8. 12-7 Measuring Irradiation Time until Metal Specimen Rupture in Sodium Cooled Reactor
    - In-Pile Creep Rupture Experiment of Cladding Materials for Fast Reactor -
  9. 12-8 Upgrading of HTTR Burnup Characteristics Evaluation Method
    - Improvement of BP Burnup Characteristics -
  10. 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-
  11. 12-10 Battle Against Water Inflow: Five-year History of Mizunami Underground Research Laboratory
    - Development of Post-Grouting Technology for Deep Shaft -

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