우수한 역학적 성능을 가진 생물체의 구조를 모방하여 고성능의 복합재료를 개발하려는 노력이 최근 활발히 이뤄지고 있다. 진주 층 구조는 구성재료 대비 월등히 높은 파괴인성을 지닌다는 점에서 촉망받는 자연 모사 구조 중 하나이다. 하지만, 진주층 모사 구조의 형상이 변형될 때 구조의 충격성능이 어떻게 달라지는지에 관한 연구는 아직 충분히 진행되지 않았다. 본 연구에서는 무작위로 변형 된 진주층 모사 복합재의 수치모델을 개발하고 충격성능을 분석하였다. 먼저, 균일한 진주층 모사 패턴에서 플레이트 판의 평면 크기 를 무작위로 변형하는 알고리즘을 개발하고 이를 활용하여 불균일한 진주층 패턴 모사 구조를 모델링하였다. 그 후, 낙하충격 시뮬레 이션을 수행하고 해당 모델의 충격거동을 에너지 흡수율과 본 미세스 응력 분포, 충격력-시간 그래프를 활용하여 평가하였다. 수치해 석결과를 바탕으로, 충돌 범위 주변 플레이트 판의 기하학적 형상이 불균일할수록 진주층 모사 구조의 내충격성이 저하됨을 입증하 였다. 이러한 진주층 모사 형상에 대한 심층적인 이해는 진주층 모사 구조의 최적설계를 수립하는 데 효율적으로 활용될 수 있을 것으 로 기대된다.

This study assessed the changes in the fiber properties of virgin and recovered fibers from lab-scale and pilot-scale depolymerization reactors based on the thermal air oxidation-resistance characteristics. Lab-scale and pilot-scale depolymerization reactors had different depolymerization volumes. Results showed that the lab-scale and pilot-scale peak solvent temperatures were 185 °C and 151 °C, respectively. The lab-scale had highest solvent temperature rate increase because of the small depolymerization volume and the dominant role of the cavitation volume. The structural properties of the recovered and virgin fibers were intact even after the depolymerization and after the pretreatment and oxidation-resistance test. We observed 1.213%, 1.027% and 0.842% weight loss for the recovered (lab-scale), the recovered (pilot-scale) and virgin fibers because of the removal of impurities from the surface and chemisorbed gases. Further, we observed 0.8% mass loss of the recovered fibers (lab-scale) after the oxidative-onset temperature because of the “cavitation erosion effect” from the dominant of the cavitation bubbles. The “cavitation erosion effect” was subdued because of the increased depolymerization volume in the pilot-scale reactor. Therefore, negligible impact of the pilot-scale mechanochemical recycling process on the structure and surface characteristics of the fibers and the possibility of reusing the recovered fibers recycling process were characteristic. Representative functional groups were affected by the thermal oxidation process. We conducted HPLC, HT-XRD, TGA– DSC, XPS, SEM, and AFM analysis and provided an extensive discussion of the test thereof. This study highlighted how misleading and insufficient small-lab-scale results could be in developing viable CFRP depolymerization process.

The detection of the genome-based antibiotic resistance gene is an essential analysis process for the purpose of verifying the safety of probiotic strains, including lactic acid bacteria. In this study, 4 analysis platforms (AMRFinderPlus, staramr, rgi, ABRicate) were used for cross-comparison of 782 genomes corresponding to 19 kinds of probiotic species notified as functional foods. As a result of the analysis, the relatively fewest number of antibiotic resistance genes were detected in strains belonging to the order Lactobacillales, and antibiotic resistance genes were detected in 322 genomes used in the case of 2 types of Enterococcus genus. In addition, the presence and type of antibiotic resistance gene detection showed a lot of difference even for the same genome sequence depending on the database and analysis algorithm used by the analysis platform. These results can be confused in evaluating the potential for transmission of antibiotic resistance genes inherent in specific lactic acid bacteria and predicting potential risks that may occur in the future. Accordingly, it is judged that the antibiotic resistance gene-related analysis criteria need to be established more clearly and specifically in the safety evaluation of probiotic bacteria.

목구조에 있어서 횡력에 저항하는 전단벽의 역할은 대단히 중요하다. 특히 이 목조 전단벽은 다양한 수종의 스터드 와 다양한 판재, 접합철물로 제작되어 재료의 성능을 특정하기가 쉽지 않다는 어려움이 있다. 따라서, 구조설계에서 초기단계에 서부터 적용해야하는 경골목조 전단벽의 환산 전단성능값을 미국, 캐나다, 일본 그리고 국내기준의 설정방법을 통하여 파악해 보고자 하였다. 분석결과 국내 경골목구조기준과 소규모 건축기준에서 기본사양으로 제시하고 있는 2×4의 스터드에 두께 11㎜ 의 OSB를 적용한 기본 전단벽의 허용전단력은 3.5~4.5 kN/m의 범위, 또한 환산 전단강성값으로는 1100~1150 kN/m정도로 설계 하는 것이 가능할 것으로 나타났다. 특히, 국내기준은 국외기준에 비하여 상대적으로 큰 전단내력을 허용하고 있는 것으로 나타났고, 현재 기준에서와 같이 북미기 준과 동일한 전단강성을 활용할 경우, 재료의 비선형거동 때문에 실제 변형량을 과소평가할 가능성이 있어, 허용응력의 설정범 위와 전단강성값의 산정기준을 조정하여야 할 필요가 있는 것으로 파악되었다.

Accurate understanding of structural integrity and chemical reactivity of UO2 disposed in deep underground sites is of importance. Owing to the specific condition of the site location, UO2 may have substantially different properties from the conventional prediction. In this study, we demonstrate that the oxidation resistivity of UO2 is considerably modified by gadolinium (Gd), which is the element of neutron absorber and a byproduct of nuclear decay of radioactive U-235. Using density functional theory calculations, we investigate how the oxidation mechanism of UO2 changes with Gd incorporation in U lattice. Our study indicates that Gd remarkably enhances the thermodynamic stability of pristine UO2 against surface oxidation via three underlying mechanisms: (i) weakens the chemical bonding of adsorbed oxygen atom (O) with U, (ii) reduces active sites (U) for oxygen adsorption, and (iii) suppresses the subsurface diffusion of adsorbed O delaying the growth of the oxide layers on the UO2. Electronic and lattice structure analyses for Gd-doped UO2 indicate that amount of charge transfer from U to O is critically reduced and the lattice of the UO2 surface is contracted. Our results provide useful information for understanding long-term stability and improving the structural integrity of UO2 through the chemical doping process.

A molten salt reactor (MSR) has considerably attracted attention due to its several advantages for the safety and efficiency over the light water reactors. Because the structural material in MSR is contacted with high-temperature liquid fuel during long-term, the excellent material for corrosion resistance is required to be applied in MSR. In this study, we evaluated the corrosion resistance for alloy 600 and 617, which are the nickel-based materials, in KCl molten salt at 800ºC for 100 h under Ar atmosphere containing less than 1 ppm of moisture and oxygen. After the corrosion experiments of alloy 600 and 617, the amount of the weight loss for them caused by the KCl molten salt were determined. In addition, the variation in the crystal structure, surface morphology, and elemental distribution was examined using X-ray diffraction and scanning electron microscopy equipped with energy dispersive X-ray spectroscopy.

HIC refers to a radwaste packaging container that can maintain integrity for more than 300 years in the general underground environment and disposal conditions in Korea. For HIC, the integrity of containers is verified according to the HIC regulation guideline for LLW and ILW disposal. Existing material tests include mechanical stability, permeability resistance, corrosion properties, chemical durability and biological resistance. In this study, a chemical durability test was conducted to prove the suitability of the HIC material by measuring the degree of chemical influence other than corrosion from the disposal environment. The chemical resistance evaluation method was used to simulate the disposal environment in the underground repository, and the amount of change in the physical properties of the degraded polymer concrete specimens according to the test time was confirmed. The technical standards considered leaching of material components, sulfation attack, acid attack, alkali, carbonate, and salt crystallization. The compressive strength and weight change of the specimens with time were checked by immersing them in a chemical solution that could leak major hazardous substances and wastes in the groundwater of the repository for several months. In addition, in order to evaluate the integrity in condition severe than the disposal environment, a flow was applied to a chemical solution having a concentration twice that of the basic chemical resistance test conditions, and the test period was extended twice to accelerate the deterioration of the specimen.

Liquid-fueled Molten Salt Reactors (MSRs) do not contain their fuel in assemblies. It is then not possible to perform traditional item counting and visual accountability of the salt fuel. These facilities are closer to bulk accounting facilities, such as reprocessing plants, and require inventory determinations based on measurements of the actinide content of salts. This can be problematic due to the difficulty of sampling and the destructive analysis of actinide-containing molten salts. Some problems arise from the unique combination of high temperature and high radiation environments present in molten salt fuels. Another challenge is the continuous change in the isotopic concentration of fuel salts due to burn-up, conversion, plating out, and online chemical processing. There is a potential for fuel stocks outside the reactor containment vessel in on-site salt processing. In terms of proliferation resistance of 233U-232Th fuel cycle, the nuclide 232U is an important nuclide in thorium fuel cycle from the standpoint of proliferation resistance, because its daughter Thallium (208Tl) is a strong gamma (2.6 MeV) emitter. The hard gamma ray is not only barrier from to nuclear material theft, but also an effective means of detecting lost fissile material. However, there is a theoretical weakness in obtaining pure 233U at the core of the initial two weeks with a concentration of 232Pu less than 1,000 ppm. Therefore, Pu separation process is one of the most sensitive parts in online reprocessing facility. The decision to use a fertile blanket should also be based on proliferation risk considerations in addition to operational parameters. MSRs can be designed without a separate fertile blanket, which should be considered. In the case of the MSFR, even if fertile blankets are used, the production of 232U is large enough to make difficult the utilization of blankets for proliferation purpose. For the liquid-fueled MSRs without fissile materials separations, many of the observations from the previous section apply, except salt processing is minimized. The reactors will still need some method of estimating total actinide content. These reactor designs reduce proliferation risk for the reactor by not separating any actinides during operation.

The purpose of this study is to investigate the distribution of toxin genes and antimicrobial resistance of Vibrio parahaemolyticus isolated from seafood in Gwangju. A total of 335 seafood, including 163 shellfish, 97 fish, and 36 mollusk, were tested in this study. As a result, V. parahaemolyticus was detected in 123 (36.7%) of 335 seafood. The tdh gene was not detected in all strains, while the trh gene was detected in 3 strains (2.4%). According to antimicrobial susceptibility test, 116 strains (94.3%) represent resistance to ampicillin, and 1 strain (0.8%) represents resistance to trimethoprim/sulfametoxazole. However, all strains were sensitive to 9 antimicrobial agents, including amikacin, chloramphenicol, tetracycline, and more. Therefore, the risk of V. parahaemolyticus isolated from seafood in Gwangju is considered low, but continuous monitoring of V. parahaemolyticus in seafood is required.