Ion-beam irradiation(IB) on HfO2 surface induced high-performance liquidcrystal(LC) driving at a 1-V threshold with vertical alignment of liquid crystals(LC). The high-k materials Atomic layer deposition was used to obtain LC orientation on ultra thin and high-quality films of HfO2 layers. To analyze surface morphological transition of HfO2 which can act as physic alignment effect of LC, atomic force micro scopy images are employed with various IB intensities. The contact angle was measured to elucidate the mechanism of vertical alignment of LC on HfO2 with IB irradiation. Contact angle measurements show the surface energy changes via IB intensity increasing.

Tin-antimony sulfide nanocomposites were prepared via hydrothermal synthesis and a N2 reduction process for use as a negative electrode in a sodium ion battery. The electrochemical energy storage performance of the battery was analyzed according to the tin-antimony composition. The optimized sulfides exhibited superior charge/discharge capacity (770 mAh g-1 at a current density of 100 mA g-1) and stable lifespan characteristics (71.2 % after 200 cycles at a current density of 500 mA g-1). It exhibited a reversible characteristic, continuously participating in the charge-discharge process. The improved electrochemical energy storage performance and cycle stability was attributed to the small particle size, by controlling the composition of the tin-antimony sulfide. By optimizing the tin-antimony ratio during the synthesis process, it did not deviate from the solubility limit. Graphene oxide also acts to suppress volume expansion during reversible electrochemical reaction. Based on these results, tin-antimony sulfide is considered a promising anode material for a sodium ion battery used as a medium-to-large energy storage source.

본 연구는 전기투석과 용매추출을 융합한 희유금속 회수 공정에서 분리막과 음이온교환막의 개질을 통해 유기상 과 수상에 대한 분리막의 낮은 젖음성 및 AEM을 통한 수소이온 투과로 인한 금속이온의 회수 효율 감소를 개선하였다. 구체 적으로, 분리막 표면 중 한면은 polydopamine (PDA) 통한 친수성 개질, 다른 면은 SiO2 또는 graphene oxide를 통한 친유성 개질을 함으로써 분리막의 젖음성을 개선하였다. 또한, 음이온교환막의 표면을 polyethyleneimine, PDA, poly(vinylidene fluoride) 등을 이용, 개질해 수분 흡수(Water uptake) 감소 및 기공구조 변화를 통해 수소이온 수송을 억제해 수소이온 투과를 억 제할 수 있다. 개질된 막 표면 형상과 화학적 특성 및 조성은 주사전자현미경과 푸리에변환 적외선 분광법을 통해 확인되었 고, 이를 구리 이온 회수 시스템에 적용해 향상된 추출 및 탈거 효율과 수소이온 수송 억제능을 확인하였다.

수산화리튬(LiOH)에 대한 수요는 현재의 대안들에 비해 환경에 대한 효율성과 안전성 때문에 매년 증가하고 있 다. 리튬은 다른 염분과 염수 호수에서 발견될 수 있으며, 나중에 합성되어 다양한 용도로 LiOH를 생성한다. 리튬 이온을 분 리 및 회수하기 위해 다양한 방법이 사용되며, 그 중 가장 일반적인 방법은 전기투석법(ED)이다. ED는 이온을 한쪽에서 다 른 쪽으로 밀어내는 구동력으로서 그 층의 전위차에 작용하는 멤브레인 기반 분리 기술이다. ED의 이온교환막(IEM)은 유체 역학적 부피에 따라 상이한 이온의 선택성이 달라지기 때문에 공정을 효율적으로 만든다. 본 총설에서는 리튬이온의 회수를 향상시키기 위한 ED와 IEM의 서로 다른 변화 전략이 논의된다.

Lithium-ion batteries (LIBs) are powerful energy storage devices with several advantages, including high energy density, large voltage window, high cycling stability, and eco-friendliness. However, demand for ultrafast charge/discharge performance is increasing, and many improvements are needed in the electrode which contains the carbon-based active material. Among LIB electrode components, the conductive additive plays an important role, connecting the active materials and enhancing charge transfer within the electrode. This impacts electrical and ionic conductivity, electrical resistance, and the density of the electrode. Therefore, to increase ultrafast cycling performance by enhancing the electrical conductivity and density of the electrode, we complexed Ketjen black and graphene and applied conductive agents. This electrode, with the composite conductive additives, exhibited high electrical conductivity (12.11 S/cm), excellent high-rate performance (28.6 mAh/g at current density of 3,000 mA/g), and great long-term cycling stability at high current density (88.7 % after 500 cycles at current density of 3,000 mA/g). This excellent high-rate performance with cycling stability is attributed to the increased electrical conductivity, due to the increased amount of graphene, which has high intrinsic electrical conductivity, and the high density of the electrode.

Complexing agents used at various nuclear facilities exist in low- and intermediate level radioactive wastes deposited in the repository site. In addition these will be generated through the degradation of the wastes such as cellulose materials. The presence of chelating agents may possibly affect the safety of the wastes repository by promoting the migration of radionuclides into geosphere. Thus, under Nuclear Safety and Security Commission’s Notice No. 2021-16, the contents of chelating agents in radioactive wastes are required to be determined for the secured disposal. UV-Vis method based on an enzymatic reaction was proved to be in adequate to analyze citric acid in radioactive wastes with complex matrix, especially for concrete. A rapid automated method using ion chromatography (IC) for analysis of citric aicd in concrete samples is developed. This automated method enables a sample solution to measure without pretreatment and a target substance to separate from other concrete admixtures. Also, the developed method here, for radioactive concrete wastes was successfully applied to real samples with lowering a limit of quantification value.

We established pretreatment method of solidified cement ion-exchange resin samples generated before 2003 in nuclear power plants for measurement of non-volatile radionuclide activity. A microwave digestion system (MDS) with mixed acid (HCl-HNO3-HF-H2O2) was used to dissolve cement and to desorb non-volatile elements such as Ce, Co, Cs, Fe, Nb, Ni, Re, Sr and U from mixed ion-exchange resin. The content of Ce, Co, Fe, Nb, Ni, Re, Sr, U and Cs after pretreatment of cement plus mixed ion-exchange resin was measured by ICP-AES and ICP-MS, respectively. As iron and strontium are also present in cement, their content after dissolving a certain amount of cement was measured by ICP-AES. All elements except Nb were quantitatively recovered. Especially since the Nb recovery was low at 72.0±2.5%, the MDS following addition of the mixed acid to the resin was operated once more for desorbing Nb from it. Finally the recovery of Nb was over 95%. This sample pretreatment method will be applied to solidified cement ion-exchange resin samples generated in nuclear power plants for assessment of radionuclide inventory.

Cardiovascular disease remains as one of the most common causes of high morbidity and mortality worldwide, despite remarkable medical advances in recent decades. Non-invasive techniques play a preeminent role in prevention of cardiovascular disease by diagnosing it at an early stage and guiding optimal patient management. Nuclear imaging is one of the most powerful means available for noninvasive diagnosis and management of poorly perfused myocardial region resulting from the cardiovascular disease. Several radionuclides are available for monitoring blood flow to cardiac tissue. The most validated radionuclides for these measurements are 13N, 15O, 99mTc, 201Tl and 82Rb. Each of 13N, 15O and 201Tl require the presence of an on-site cyclotron, whereas, 82Rb and 99mTc require only a generator. Rubidium (Rb) is an alkali metal ion that acts biologically like potassium and accumulates in cardiac muscle tissue. Rb has a rapid blood clearance profile which allows the use of 82Rb. It also has an ultra-short physical half-life of 75 sec for non-invasive evaluation of regional cardiac blood flow. There are several advantages of 82Rb over other radionuclides. Having a short half-life significantly reduces the radiation dose to the patient. In addition, 82Rb is a positron emitter, which gives the full advantages of PET such as image quantification with superior sensitivity. Several reports have shown superior diagnostic performances of 82Rb-PET over conventional 99mTc-SPECT. 82Rb can be produced from a generator system by the decay of its 25.6-day half-life parent 82Sr. However, the 82Sr parent is difficult to prepare. In routine generator production, certain purity is required to meet the specification of the product. Since there has been no the use of 82Rb radionuclide for research or medical purpose in Korea, we have plans to produce 82Sr with certain purity and develop a 82Sr/82Rb generator system. These studies can also be applied to remove radioactive Sr from radioactive waste waters. Because ion exchange resin, used for purification of 82Sr from impurities, is also utilized to trap radioactive Sr2+ ions from radioactive waste water. After Fukushima Daiichi nuclear accident, interest in the treatment of radioactive waste water has surged. As one of main fission products of nuclear reactor, 90Sr has been regarded as a hazardous radionuclide with half-life of about 29 years. Therefore, the investigation on ion exchange resin is important for removal of 90Sr from radioactive waste water. Here, we optimized 82Sr purification method using ion exchange resin to establish the most suitable procedure.

HANARO, a multi-purpose research reactor, uses a reflector as heavy water to obtain high neutron flux. Therefore, two ion exchangers were installed to manage the heavy water quality of the reflector system. The operator of HANARO manages it according to the limit value (Conductivity: less than 0.5 mS/m, pH: 5.5~6.5), and if the limit value is not satisfied, the resin must be replaced. The reflector system is in the enclosed structure and it is designed to delay the release of tritium to the outside. Tritium is produced by a nuclear reaction between neutrons and deuterium. Tritium is inhaled into the body in the form of water or vapor, which is likely to cause internal exposure problem. In addition, since tritium spreads to other regions, thorough management is required. Therefore, HANARO measures and manages tritium in Rx and RCI using the bubbler collection method. In this paper, the change in the behavior of tritium due to the replacement of the reflector ion exchanger resin was analyzed. Due to the increase in conductivity of the reflector, the ion exchanger resin was replaced on March 3, 2022. Therefore, the concentration of tritium was measured to be about 5 times higher than usual. It did not exceed the emission limit, and the concentration values of tritium is stably managed by constant monitoring and analysis.

This study aimed to remove uranium (U(VI)) ions from sulfate-based acidic soil-washing effluent using the ion-exchange method. For effective ion exchange of U(VI) ions under acidic conditions, one chelate resin (Purolite S950) stable under low pH conditions and two anion-exchange resins (Ambersep 400 SO4 and 920U SO4) used in sulfuric acid leaching systems were selected. The exchange performance of the three selected ion-exchange resins for U(VI) ions was evaluated under various experimental conditions, including ion-exchange resin dosages, pH conditions, reaction times, and reaction temperatures. U(VI) ion exchange was consistent with the Langmuir model and followed pseudo-second-order kinetics. Thermodynamic experiments revealed that the U(VI) ion exchange by the ion-exchange resins is an endothermic and spontaneous process. On the other hand, U(VI) ions was effectively desorbed from the ion-exchange resins using 0.5 M H2SO4 or Na2CO3 solution. Overall, on the basis of the results of the present study, we propose that Purolite S950, Ambersep 400 SO4, and Ambersep 920U SO4 are ion-exchange resins that can be practically applied to effectively remove U(VI) ions from sulfate-based acidic soil-washing effluents.

리튬-이온 전지 기술의 발전과 함께 다량의 리튬 사용에 따라 리튬-이온 전지에 대한 수요와 공급의 균형이 무너지고 있으며, 따라서 리튬을 대체할 수 있는 차세대 이차 전지의 개발이 필요해지고 있다. 최근 친환경적이며, 값싸며 안전 하고, 다가의 전자를 활용할 수 있는 아연 이온을 활용하는 수계 아연-이온 전지가 주목받고 있다. 그럼에도 불구하 고 아연-이온 전지에 사용될 수 있는 전류 집전체에 대한 개발 연구는 거의 없으며, 특히 현재 사용되고 있는 금속 기반의 전류 집전체는 그 무게가 무거워 실용적으로 사용되기 힘들다. 본 연구에서는 접착 특성이 매우 우수한 키틴 바인더를 사용하여 집전체 없이 지탱이 가능한 전극을 개발하였으며 아연-이온 전지에서의 그 특성을 평가하였다. 전 극 제조는 전통적인 코팅법과 스핀 코팅법을 사용하여 비교하였으며, 스핀 코팅이 더 균일한 전극 형성과 함께 더 우 수한 배터리 성능을 나타냄을 확인하였다.

One of the promising supercapacitors for next-generation energy storage is zinc-ion hybrid supercapacitors. For the anode materials of the hybrid supercapacitors, three-dimensional (3D) graphene frameworks are promising electrode materials for electrochemical capacitors due to their intrinsic interconnectivity, excellent electrical conductivity, and high specific surface area. However, the traditional route by which 3D graphene frameworks are synthesized is energy- and time-intensive and difficult to apply on a large scale due to environmental risks. Here, we describe a simple, economical, and scalable method of fabricating grafoil (GF) directly into a graphite–graphene architecture. Both synthesizing of a porous structure and functionalization with interconnected graphene sheets can be simultaneously achieved using electrochemically modified graphite. The resultant graphite electrode provides a high capacitance of 140 mF/cm2 at 1 mA/cm2, 3.5 times higher than that of pristine grafoil, keeping 60.1% of its capacitance when the current density increases from 1 to 10 mA/cm2. Thus, the method to produce 3D graphene-based electrodes introduced in the current study is promising for the applications of energy storage devices.

이온교환막(IEM)은 다양한 종류의 단가이온과 다가이온을 분리하기 위해 사용되는 막의 한 종류로, 배터리, 연료 전지, 염화물-알칼리 공정 등에 사용된다. 이온교환막을 통한 막분리는 전기 구동력을 기반으로 한 녹색 분리 방식이며, 해수 담수화와 수처리 분야에서 떠오르는 방식이다. 전기투석(ED)은 양이온과 음이온이 이온교환막을 따라 선택적으로 이동하는 기술이다. 음이온 교환막(AEM)은 전기투석의 중요한 구성 요소 중 하나이며, 공정 효율을 향상시키는 데 상당한 역할을 한 다. 이온교환막에 가교결합을 도입하면 자유 부피의 감소로 인해 이온 선택 분리 성능이 향상된다. 역삼투(RO) 공정을 통한 해수 담수화 시 RO 농축수에 용해된 염이 다량 존재한다. 따라서 1가 양이온 선택막으로 구성된 전기투석 공정은 오염을 줄 이고 막 플럭스를 개선한다. 이 검토는 전기투석, 음이온 교환막, 그리고 양이온 교환막의 세 부분으로 나뉜다.