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 Applied Chemistry
  • 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

研究分野

  • Energy Nuclear engineering

論文

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

Applicability of polyvinylpolypyrrolidone adsorbent to treatment process of wastes containing uranium

Studies on electrochemical behavior of uranium species in choline chloride-urea eutectic for developing electrolytically treating method of uranium-bearing wastes

Feasibility studies on electrochemical recovery of uranium from solid wastes contaminated with uranium using 1-butyl-3-methylimidazorium chloride as an electrolyte

Extraction mechanisms of uranyl ions by 1-butyl-3-methylimidazolium nonafluorobutanesulfonate containing N-dodecyl-2-pyrrolidone

Application of Ionic Liquid as a Medium for Treating Waste Contaminated with UF4

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

ResearchMapへ移動します

Inquiries about coverage or research

Inquiries about coverage

Public Affairs Division Public Affairs and Communications Department

Tel. 0463-63-4670(direct dialing)