浅沼 徳子

Noriko Asanuma

  • 准教授
  • 学位:博士(工学)

基本情報

所属

  • Undergraduate School of Engineering / Department of Nuclear Engineering
  • Graduate School of Engineering / Course of Applied Science

研究と関連するSDGs

  • Affordable and Clean Energy
  • Responsible Consumption and Production
  • Climate Action

詳細情報

論文

STRAD Project for Systematic Treatments of Radioactive Liquid Wastes Generated in Nuclear Facilities

Application of Ionic Liquid as a Medium for Treating Waste Contaminated with UF_4

Electrochemical Studies on Uranyl(VI) Chloride Complexes in Ionic Liquid, 1-Butyl-3-methylimidazolium Chloride

Electrochemical properties of uranyl ion in ionic liquids as media for pyrochemical reprocessing

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 UO2 pellet containing simulated fission products in ammonium carbonate solution

New approach to the nuclear fuel reprocessing in non-acidic aqueous solutions

Anodic dissolution of UO2 in aqueous alkaline solutions

講演・口頭発表等

  • Development of treatment processes of uranium contaminated wastes using adsorbent with high selectivity to uranium(3):Adsorption behavior of uranium onto the PVPP adsorbent
  • Development of treatment processes of uranium contaminated wastes using adsorbent with high selectivity to uranium(1):Dissolution behavior of sludge containing uranium into inorganic acid
  • Development of treatment processes of uranium contaminated wastes using adsorbent with high selectivity to uranium:(2)Adsorption behavior of uranium onto the PVPP adsorbent
  • A study on an extraction mechanism of uranyl ions extracted by BMINfO containing pyrrolidone compounds
  • Molybdenum extraction from spent nuclear fuel by using pyridine resin:Distribution coefficients of molybdenum and zirconium on pyridine resin
  • A study on an extraction mechanism of uranyl ions extracted by BMINfO containing NDP
  • Study on extraction species of uranyl ion in BMINfO used as a solvent for extraction
  • Development of uranium recovery technique from materials contaminated with uranium using ionic liquid:electrolytic recovery of uranium from ionic liquid
  • Redox behavior of palladium ion in eutectic solvents based on choline chloride
  • Development of uranium recovery technique from uranium contaminated materials by using ionic liquids:(3) Extraction of uranium to hydrophobic ionic liquids
  • Experiencing management program of an experimental and research project in nuclear energy:(1) An outline of the SWEEP program
  • Experiencing management program of an experimental and research project in nuclear energy:(4) Review of the SWEEP program
  • Development of uranium recovery technique from uranium contaminated materials by using ionic liquids:(2) Redox properties of uranium
  • Development of uranium recovery technique from uranium contaminated materials
  • Application of ionic liquids to pyrochemical reprocessing methods (3):Dissolution of uranium oxides and simulated FP metal ions
  • Application of ionic liquids to pyrochemical reprocessing methods (4):Electrochemical behavior of uranyl ion and simulated FP metal ions
  • Application of ionic liquids to pyrochemical reprocessing methods (2):Electrochemical behavior of uranyl ion
  • Application of ionic liquids to pyrochemical reprocessing methods(1):Dissolution of uranium oxide fuels by using Cl2
  • Development of a simple reprocessing process based on dissolution of fuels in aqueous carbonate solutions:Investigation of processes based on dissolution of U3O8 by adding H2O2
  • Development of a simple reprocessing process based on dissolution of fuels in aqueous carbonate solutions:Dissolution of U3O8 by anodic oxidation and by adding H2O2

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