이 연구의 목적은 척추 자기공명영상 검사 시, 검사시간을 단축할 수 있는 기법인 SENSE와 CS-SENSE를 경추, 흉추, 요추 검사 시 어떤 기법을 적용하는 것이 효과적인지 알아보기 위함이다. 본 연구는 2022년 10월부터 2023년 3월까지 척추질환 및 의심 환자 102명을 대상으로 분석하였다. 사용된 장비는 필립스 사의 3.0T Ingenia Elition X와 20채널 두경부 코일과 44 채널 척추 코일을 사용하였다. 본 연구는 축상 T2강조 고속스핀에코를 SENSE와 CS-SENSE factor 1.5, 2, 3으로 각각 영상을 획득하고, 정량평가는 신호대잡음비와 대조대잡음비를 각 factor 별로 대응 표본 t-test를 진행하였고, 정성평가는 2명의 평가자의 평가점수를 Kruskal-wallis test로 비교하였다. 정량평가 결과, SENSE보다 CS-SENSE가 신호대잡음비와 대조대잡음비가 높게 나왔다. 정성평가 결과, 경추, 요 추는 CS-SENSE 사용 시 평가점수가 높게 나왔고, 흉추는 SENSE 사용 시 평가점수가 높게 나왔다. 결론적으로 척추 MRI 검사 시, 경추, 요추는 CS-SENSE를, 흉추는 SENSE를 사용하는 것이 효과적이다.

Efficient Li-ion transport in anode materials is paramount for electric vehicles (EVs) and energy storage systems. The rapid charging demands of EVs can lead capacity decay at high charging rate. To overcome this challenge, we focus on graphite geometric characteristics that effect to interparticle space. We interpret the correlation between the utilization of the electrode and the interparticle space where solvated Li-ion transports in liquid electrolyte. To introduce variability into this space, two main coke precursors, coal cokes and petroleum cokes, were prepared and further categorized as normal cokes and needle cokes. Manufactured graphite samples were observed with distinct geometric characteristics. In this study, investigates the impact of these geometric variations on electrochemical performance, emphasizing rate capability and cycle stability during fast charging. By analyzing the transport properties of electrochemical species within these graphite samples, we reveal the critical role of morphology in mitigating concentration polarization and side reaction, such as Li-plating. These findings offer promising contribution for the development of advanced anode materials, in fast-charging condition in Li-ion.

This study aimed to investigate the effects of antioxidant and anti-inflammatory activities of heat-killed lactic acid bacteria (LAB) produced under different temperature conditions. Regarding probiotic properties, Limosilactobacillus fermentum SMF743 and Lactiplantibacillus plantarum SMF796 isolated from kimchi showed strong acid and bile salt resistance, adhesion activity onto HT-29 cells, and antimicrobial activity against pathogenic bacteria. Based on the results of thermal death time and temperature, heat-killed LAB cells (1 mg/mL) were prepared by heating at 70oC (180 min), 80oC (120 min), 100oC (30 min), and 121oC (15 min). The heat-killed SMF743 and SMF796 showed significantly higher DPPH and ABTS radical scavenging activities than live cells (p<0.05). The heat-killed SMF743 and SMF796 at 70oC or 121oC revealed stronger DPPH and ABTS radical scavenging activities and inhibition of nitric oxide production than those at 80oC or 100oC. Furthermore, heat-killed SMF743 and SMF796 at 121oC significantly reduced the gene expression levels of tumor necrosis factor-, inducible nitric oxide synthase, and cyclooxygenase- 2 up to 53.33%, 58.67%, and 83.67%, respectively, in lipopolysaccharide (LPS)-induced RAW264.7 cells (p<0.05). These results suggest that heat-killed L. fermentum SMF743 and L. plantarum SMF796 can be used as natural antioxidants and anti-inflammatory agents.

Se-79, a fission product of uranium, is present in spent nuclear fuel. Selenium is volatilized from the spent nuclear fuel during the pretreatment of pyroprocessing, and a filter composed of calcium oxide can capture gaseous selenium in the form of CaSeO3. Because Se-79 has a long half-life (3.27E5 years) and selenite ions have high mobility in groundwater, they must be immobilized in a chemically stable form for final disposal. This study used a composition of 50 TeO2 - 10 Al2O3 - 10 B2O3 - 10 Na2O - 10 CaO - 10 ZnO (mol%). High-purity powders of TeO2, Al2O3, H3BO3, Na2CO3, CaCO3, and ZnO were used as glass precursors. The mixed powders were placed in alumina crucibles and melted in an electric furnace under an ambient atmosphere at 800°C for 1 h before being cast on a carbon mold. The obtained glasses were ground into fine powders and then mixed with CaSeO3 powders. The powders were melted in alumina crucibles at 800°C for 1 h. To simulate a seleniumcaptured calcium filter, CaSeO3 was synthesized by a precipitation method using sodium selenite (Na2SeO3) and calcium nitrate (Ca(NO3)2) solutions. The glass samples were analyzed by an X-ray diffractometer (XRD). Retention of Se in tellurite glasses was analyzed by an X-ray fluorescence spectrometer (XRF) and inductively coupled plasma (ICP). The chemical durability of tellurite glass was evaluated through the PCT method.

Radioactive cesium is a heat generated and semi-volitile nuclide in spent nuclear fuel (SNF). It is released gasous phase by head-end treatment which is a pretreatment of pyroprocessing. One of the capturing methods of gasous radioactive cesium is using zeolite. After ion-exchanged zeolite, it is transformed to ceramic waste form which is durable ceramic structure by heat treatment. Various ceramic wasteforms for Cs immobilization have been researched such as cesium aluminosilicate (CsAlSi2O6), cesium zirconium phosphate (CsZr2(PO4)3), cesium titanate (CsxAlxTi8-xO16, Cs2TiNb6O18) and CsZr0.5W1.5O6. The cesium pollucite is composed to aluminosilicate framework and cesium ion incorporated in matrix materials lattices. Many researchers are reported that the pollucite have high chemical durability. In this study, the Cesium pollucite was fabricated using mixtures of aluminosilicate denoted Absorbent product (AP) and Cs2CO3 by calcination and pelletized by cold pressing. The characterization of fabricated pollucite powder and pellets was analyzed by XRD, TGA, SEM, SEMEDS and XRF. The chemical durability of pollucite powder was evaulated by PCT-A and ICP-MS and OES. Thus, the optimal pressure condition without breaking the pellets which is low Cs2O/AP ratio and pelletizing pressure was selected. The long-term leaching test was performed using MCC-1 method for 28 days with the fabricated pollucite pellets. The leachate of leaching test was allard groundwaster and Deionized water and replaced 5 contact periods which is 3 hours, 3 days, 7 days, 14 days and 28 days and analyzed by ICPMS. The leaching rate was shown two stages. The first stage was rapid and relatively large amount of nuclides were leached. The leaching rate was decreased in the second stage. The fractional release rate of this study was shown same trend. These results were similar to previous studies.

Radioactive Cesium is fission products of spent nuclear fuelwith high heat generating nuclide, having a 30 years half-life. Particularly, it is important to make stable waste form because Cs-137 have high solubility and mobility at ground water. The ceramic waste form has higher thermal and structural stability and lower solubility than glass and cement waste form. Various ceramic waste forms for Cs immobilization have been researched such as aluminosilicate (CsAlSi2O6), phosphate (CsZr2(PO4)3), titanate (CsxAlxTi8-XO16) and CsZr0.4W1.5O6. Cs pollucite is incorporated radio-Cesium to aluminosilicate framework by inorganic ion-exchange with zeolite. Therefore, it is an extremely stable structure. In previous study, we are prepared Cs pollucite pellet with various ratio of Cs precursor/matrix materials, and attempted to evaluate applicability as ceramic waste form. Cs pollucite is produced by mixing Mullite and SiO2 obtained by heat treatment Kaolinite with Cs2CO3 in ratios of 0.5, 0.6, 0.7, 0.8. Optimized ratio was 0.5 revealed single pollucite phase and the others exhibited CsAlSiO4 phase with pollucite. Cs pollucite of ratio 0.5 was pelletized under various conditions and evaluated performance as waste form. herein, the pellets were cracked on surface and edges broken. Therefore, Cs pollucite having high ratio of matrix materials contained Si and Al was prepared and pelletized, and then waste form was evaluated. The Cs pollucite powder is ratio of Cs precursor/matrix materials were 0.1, 0.2, 0.3, 0.4. Pollucite powder was mixed with 1.5, 2.0wt% Polyvinyl alcohol as binder, and dried at 70°C for overnight. Afterward, these powders obtained were pressed using punch-die apparatus at 50, 100 bar for 1 hour and the pellets with about dia. 25 mm and height 10 mm was acquired. These pellets were sintered at 1,400°C for 5 hours. Subsequently, the waste forms were evaluated physicochemical test such as compression strength, thermal conductivity, thermal expansion and leaching properties analysis.