山本一良 | 名古屋大学工学研究科マテリアル理工学専攻

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著作論文

4. トリチウムシステム( TFTRのDT実験)
Recovery of Metals from Simulated High-Level Radioactive Waste Glass through Phase Separation
超臨界流体からのウランの逆抽出に関する研究
超臨界直接抽出法による再処理プラントの概念と特徴
COE21プログラムにおける原子力研究
Selective Extraction of Uranium from a Mixture of Metal or Metal Oxides by a Tri-n-butylphosphate Complex with HNO_3 and H_2O in Supercritical CO_2
Densities of Supercritical Fluids Containing CO_2 and Tri-n-butylphosphate
Stoichiometric Relation for Extraction of Uranium from UO_2 Powder using TBP Complex with HNO_3 and H_2O in Supercritical CO_2
Liquid Metal Extraction for Removal of Molybdenum from Molten Glass Containing Simulated Nuclear Waste Elements
Removal of Platinum Group Metals Contained in Molten Glass Using Copper
Extractability of Metals in Municipal Solid Wastes Fly Ash Using Supercritical CO_2 Containing Cyanex 302
Decontamination of Radioactive Contaminants from Iron Pipes using Reactive Microemulsion of Organic Acid in Supercritical Carbon Dioxide
Generation of Nitrous Acid by Ultrasound Irradiation in the Organic Solution Consisting of Tri-n-butylphosphate, Nitric Acid and Water
Preliminary Experiments on Hydrogen Isotope Separation by Water-Hydrogen Chemical Exchange under Reduced Pressure
Isotope Separation of H_2-HD Gas Mixture with "Cryogenic-Wall" Thermal Diffusion Column with a Heated Tube
Dissolution Behavior of Uranium Oxides with Supercritical CO_2 Using HNO_3-TBP Complex as a Reactant
Isotopic Approximations to Thermal Diffusion Factor and Ordinary Diffusion Coefficient in a Mixture of More than 4 Components
New Method for the Removal of Uranium from Solid Wastes with Supercritical CO_2 Medium Containing HNO_3-TBP Complex
Estimation of Hot Wire Temperature of Thermal Diffusion Column by the Pressure Change after Turning on Electricity
Effect of Cold Wall Temperature of Thermal Diffusion Column on ^N^N-^N_2 Isotope Separation
水素同位体分離研究の現状
Electrochemical Studies on Uranium in Presence of Organic Acids
Sorption of Eu(III) on Pseudomonas fluorescens in the Presence of Citric Acid
Hydrogen Extraction Characteristics of Proton-conducting Ceramics under a Wet Air Atmosphere for a Tritium Stack Monitor
Effect of Plated Platinum Electrode on Hydrogen Extraction Performance Using CaZrO_3-based Proton-Conducting Ceramic for Tritium Recovery System
Hydrogen Extraction Using One-end Closed Tube Made of CaZrO_3-based Proton-conducting Ceramic for Tritium Recovery System
核エネルギーは未来への夢を与えられるか
熱拡散法による同位体分離の最近の進歩

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