スポンサーリンク
Research Laboratory For Nuclear Reactor Tokyo Institute Of Technology | 論文
- Measurement and Analysis of Reactivity Worth of ^Np Sample in Cores of TCA and FCA
- Transmutation of ^Sn in Spallation Targets of Accelerator-Driven Systems
- Ebola virus VP40 drives the formation of virus-like filamentous particles along with GP
- A Study on Zinc Isotope Fractionation in a Benzo Crown Resin/Acetone System
- Zinc Isotope Separation by Phenol Formaldehyde Type 15-Crown-5 Resin in Organic Solvents
- ^Cm Transmutation in Accelerator-Driven System
- Neutron Excess Generation by Fusion Neutron Source for Self-Consistency of Nuclear Energy System
- 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
- Effect of Transplutonium Doping on Approach to Long-life Core in Uranium-fueled PWR
- Long-life Water Cooled Small Reactor with U-Np-Pu Fuel
- Accumulation and Transmutation of Spallation Products in the Target of Accelerator-Driven System
- Fusion-Driven Transmutation of Fission Product Cesium in its Elemental Form
- Transmutation of Zirconium-93 in High-flux Blanket of Fusion Neutron Source
- 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
- Anodic Dissolution of UO_2 Pellet Containing Simulated Fission Products in Ammonium Carbonate Solution
- Synthesis of Uranium Oxide from Uranyl Nitrate in Supercritical Fluids Recovery of Uranium from Liquid Wastes by Supercritical Treatment
- Application of Ionic Liquid as a Medium for Treating Waste Contaminated with UF_4