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Res. Lab. For Nuclear Reactors Tokyo Inst. Of Technol. | 論文
- Influence of raw powder size, reaction temperature, and soaking time on synthesis of SiC/SiO_2 coaxial nanowires via thermal evaporation
- On Void Reactivity Limitation for the Core Loaded with Mixed Nitride Fuels
- Study of the Self-Controllability for the Fast Reactor Core with High-Thermal-Conductivity Fuel
- Long-Term Integrity of Waste Package Final Closure for HLW Geological Disposal, (I) : Points at Issue Concerning 1,000 Years Containment Capability of Overpack
- Dissolution mechanisms of β-tricalcium phosphate doped with monovalent metal ions
- Synthesis and characterization of hydroxyapatite using polymerized complex method by chelation of calcium ions with organic phosphonic acid(Aqueous Solution Science for Ceramic Processing II)
- Surface Property Change of the Silicon Carbide Ceramics during the Space Exposure for Two Years
- Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (I) : Major Targets and Development Strategies of the Evaluation Methods
- Inherent Protection of Plutonium by Doping Minor Actinide in Thermal Neutron Spectra
- Denaturing of Plutonium by Transmutation of Minor-Actinides for Enhancement of Proliferation Resistance
- Electrochemical Properties of Uranyl Ion in Ionic Liquids as Media for Pyrochemical Reprocessing
- Immobilization of strontium, cesium and rhenium into α-SiAlON ceramics assisted with co-doping of yttrium(SiAlons and Non-oxides)
- Development of Advanced Reprocessing System Based on Precipitation Method Using Pyrrolidone Derivatives as Precipitants : Precipitation Behavior of U(VI), Pu(IV), and Pu(VI) by Pyrrolidone Derivatives with Low Hydrophobicity
- Solubility of Uranyl Nitrate Precipitates with N-Alkyl-2-pyrrolidone Derivatives (Alkyl = n-Propyl, n-Butyl, iso-Butyl, and Cyclohexyl
- A Study on Precipitation Behavior of Plutonium and Other Transuranium Elements with N-Cyclohexyl-2-pyrrolidone for Development of a Simple Reprocessing Process
- Anodic Dissolution of UO_2 Pellet Containing Simulated Fission Products in Ammonium Carbonate Solution
- Long-Term Integrity of Waste Package Final Closure for HLW Geological Disposal, (III) : Applicability of Electron Beam Welding to Overpack Final Closure
- Extraction of Uranium(VI) from Nitric Acid Solution Using Pyrrolidone Derivatives
- Long-Term Integrity of Waste Package Final Closure for HLW Geological Disposal, (IV) : Influence of Welding and Prediction of Long-Term Integrity of Weld Joint
- Synthesis of Uranium Oxide from Uranyl Nitrate in Supercritical Fluids Recovery of Uranium from Liquid Wastes by Supercritical Treatment
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