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Japan Nuclear Cycle Development Institute | 論文
- Thermal Neutron Capture Cross Section of Palladium-107
- Cross Section of Thermal-Neutron Capture Reaction by ^Tc
- Fabrication Technology for MOX Fuel Containing AmO_2 by an In-cell Remote Process
- Measurements of Neutron Capture Cross Section of ^Np for Fast Neutrons
- 02-O-10 Evaluation of Compaction Behavior by Observation of Internal Structure in Granules Compact
- Management of Plutonium Content based on Reactivity of Each Plutonium Isotope
- Measurement of Neutron Capture Cross Section Ratios of ^Cm Resonances Using NNRI
- Effect of Pulse Electrolysis on Morphology of Co-Deposited MOX Granules
- Plutonium Precipitation in the MOX Co-deposition Tests for the Oxide Electrowinning Process
- Core Modification to Improve Irradiation Efficiency of the Experimental Fast Reactor Joyo
- Adaptive Pulse Shaping of Femtosecond Laser Pulses in Amplitude and Phase through a Single-Mode Fiber by Referring to Frequency-Resolved Optical Gating Patterns(Optics and Quantum Electronics)
- An Assessment of the Multi-stage Counter Current Extraction of TRUs from Spent Molten Salt, into Liquid Metal
- Preliminary Tube Manufacturing of Oxide Dispersion Strengthened Ferritic Steels with Recrystallized Structure
- Multi-Wavelength Holographic Interferometry Using the White-Light Laser
- Experimental Analysis of Classical Arago Point with White-Light Laser : Optics and Quantum Electronics
- Low Current Efficiency in MOX Deposition Tests
- ICONE11-36084 DEVELOPMENT OF THE MAREC PROCESS FOR HLLW PARTITIONING USING A NOVEL SILICA-BASED CMPO EXTRACTION RESIN
- Analysis of Curium in Mixed Oxide Fuel Irradiated in the Experimental Fast Reactor JOYO for the Evaluation of Its Transmutation Behavior
- Measurement of Burnup in FBR MOX Fuel Irradiated to High Burnup
- Analysis of Irradiated ^Np in the Experimental Fast Reactor JOYO for the Evaluation of its Transmutation Behavior in a Fast Reactor