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

詳細情報

研究分野

Energy Nuclear engineering

論文

Capacitors Consisting of an Aqueous Electrolyte of the Widest Potential Window - Development towards the Recovery of Regenerating Energy of Automobiles

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

An aqueous electrolyte of the widest potential window and its superior capability for capacitors

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

Adsorption behavior of amidoxime resin for separating actinide elements from aqueous carbonate solutions

Simple reprocessing process based on anodic dissolution of fuels in aqueous carbonate solution and purification of U and Pu by amidoxime resins

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

Anodic dissolution of UO2 in aqueous alkaline solutions

Study on a nuclear fuel reprocessing system based on the precipitation method in mild aqueous solutions

講演?口頭発表等

Uranium separation from simulated silica sludge using Na2CO3 solution
Adsorption behavior of iodide ion by bismuth hydroxide nitrate and Mg-Al layered double hydroxide
Adsorption behavior of chloride ion by bismuth hydroxide nitrate and Mg-Al layered double hydroxide
Fundamental study on thorium fuel reprocessing by using phosphate-type fluorous extractant/ fluorous solvent and TOMAC/OMITf2N extraction systems
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