Removal of Th4+ Ions from Aqueous Solutions by Graphene Oxide

来源 :The 2nd China-Japan Academic Symposium on Nuclear Fuel Cycle | 被引量 : 0次 | 上传用户：xzljx

【摘要】

：

Graphene oxide (GO) [1] is prepared through the exfoliation of the oxidized graphite, and can incorporate various oxygen-containing functional groups (hydroxyl, epoxide, carbonyl, carboxyl groups) on

【作者】

：

Ning Pan Yongdong Jin Chuanqin Xia

【机构】

：

College of Chemistry, Sichuan University, Chengdu, 610064, P.R.China

【出处】

：

The 2nd China-Japan Academic Symposium on Nuclear Fuel Cycle

【发表日期】

：

2013年1期

下载到本地 , 更方便阅读

下载此文赞助VIP

声明 : 本文档内容版权归属内容提供方 , 如果您对本文有版权争议 , 可与客服联系进行内容授权或下架

论文部分内容阅读

Graphene oxide (GO) [1] is prepared through the exfoliation of the oxidized graphite, and can incorporate various oxygen-containing functional groups (hydroxyl, epoxide, carbonyl, carboxyl groups) on its surface.The presence of these oxygen-containing functional groups is well-suited for interaction with cations, which also makes GO hydrophilic and highly negatively charged in water [2].

其他文献

Novel Pillar[5]arene-Based Phosphine Oxides as Extractants for the Segregation of f-Block Elements f

Three pillar[5]arene-based phosphine oxides tethered with ten chelating groups on both sides of the pillar were synthesized.These macrocycles were found to demonstrate high efficiency and selectivity

会议

Adsorption of Th4+ from aqueous solution onto Poly(N,N-diethylacrylamide-co-acrylic acid) Microgels

Thorium is used as a fertile material for producing nuclear fuel.Since thorium is more abundant than uranium, some nuclear reactor designs incorporate thorium in their fuel cycle.It may also be used d

会议

Recovery of 233U from irradiated thorium oxide using 5% TBP as extractant

As the rapid increase of energy demand all over the world, a considerable interest is generated in the use of thorium as a potential source of fissile material in nuclear energy.Compared with uranium-

会议

Preparation of anion exchanger by pre-irradiation grafting method and its adsorptive removal of Rhen

99Tc is a long-lived, β-emitting fission product with a half-life of 2×105 years and a relatively high fission yield (6.3％ of 235U).Removal of this isotope from spent nuclear fuel waste streams is imp

会议

Solid phase extraction using N-doped carbonaceous covalent organic frameworks for treatment of urani

Uranium is a well known key nuclide in nuclear fuel cycling.Over the past few decades,lots of work has been done to selective separation of uranium present in nuclear fuel effluents,mine tailings, sea

会议

Synthesis and Characterization of UO22+-ion Imprinted Polymer for Separation and Preconcentration of

Molecular imprinting technology (MIT) has been studied extensively due to its high selectivity and good affinity for the target molecule.As a branch of molecular imprinted polymer, ion-imprinted polym

会议

Study on the Properties of isoBu-BTP/SiO2-PAdsorbent in the Separation of Minor Actinides

The selective separation of the minor actinides (neptunium, americium and curium) and their subsequent transmutation into shorter-lived or stable nuclides in advanced nuclear reactors could have a sig

会议

Extraction of Thorium(Ⅳ), Uranium(Ⅵ) and Rare Earths with NTAamide

Thorium is three times more abundant as compared to uranium in nature and is an easily exploitable nuclear resource.In recent years, molten salt reactor (MSR) as one of the Generation-Ⅳ nuclear power

会议

Adsorption and Separation Characteristics of Thorium from Nitric Acid Solution Using Silica-Based An

Todays reactors bum essentially uranium-235 and they only use about 1％ of the natural uranium [1].For this reason, uranium reserves cannot supply the needs of reactor operation for quite a long time.T

会议

Adsorption and elution of rhenium (Ⅶ)with a porous silica-based anion exchanger AR-01

Rhenium is an extremely rare metal with high melting point.It plays an important role in chemical and metallurgical industries.However, the abundance of rhenium is quitelow and there is no independent

会议

Removal of Th4+ Ions from Aqueous Solutions by Graphene Oxide

其他学术论文