In this study, we employed a small-scale experiment to demonstrate the introduction of a thin copper heat dissipation plate into a bentonite buffer layer of an engineered barrier system. This experiment designed for spent nuclear fuel disposal can effectively reduce the maximum temperature of the bentonite buffer layer, and ultimately, make it possible to reduce the area of the disposal site. For the experiment, a small-scale engineered barrier system with a copper heat dissipation plate was designed and manufactured. the thickness of the cylindrical buffer was about 2 cm, which was about 1/20 of KAERI Repository System (KRS). At a power supply of 250 W, the maximum buffer temperature reduced to a mere 1.8°C when the thin copper plate was introduced. However, the maximum surface temperature reduced to a remarkable 9.1°C, when a U-collar copper plate was introduced, which had a good contact with the other barrier layers. Consequently, we conclude that the introduction of the thin copper plate into the engineered barrier system for spent nuclear fuel disposal can effectively reduce the maximum buffer temperature in high-level radioactive waste disposal repositories.
본 연구는 대학교에서 국악을 전공한 20~30대의 진로장벽과 진로 스트레스의 관계에서 진로성숙도의 매개효과를 검증하기 위한 목적으로 진행되었다. 이를 위해 전국의 20~30대 국악전 공자를 대상으로 온라인 설문조사를 실시하였으며 178부의 유 효응답을 분석하였다. 연구결과 첫째, 대상자들의 진로장벽과 진로성숙도의 평균은 3점 이상으로 보통 이상으로 나타났다. 둘째, 주요 변인 간 상관관계 분석을 통해 진로장벽은 진로 스 트레스에 높은 정적 상관관계를 보였고, 진로장벽과 진로성숙 도는 유의한 부적 상관관계로 나타났다. 진로성숙도는 하위요 인별로는 영향의 방향성이 다른 것으로 나타났으나 전체적으로 는 진로 스트레스에 부의 영향을 미치는 것으로 확인되었다. 셋째, 진로장벽과 진로 스트레스의 관계에 있어 매개변수인 진 로성숙도의 매개효과가 통계적으로 유의하지 않은 것으로 확인 되었다. 이를 바탕으로 본 연구의 한계점과 후속 연구를 위한 제언을 논의하였다. 연구결과를 기초로 국악전공자의 개인적 문제와 불안정한 직업 환경, 대학 내 진로지도의 부족 등 환경 적 문제의 개선을 위한 진로 연구가 촉진되기를 기대한다.
본 연구의 목적은 대학생이 지각한 진로장벽과 진로적응성의 관계에 서 성격강점과 진로결정자기효능감의 순차적 매개효과를 알아보는데 있 다. 이를 위해 2020년 9월 15일부터 한 달간 온라인 설문조사에 참여 한 4년제 대학 재학 남녀 대학생 385명의 자료를 분석에 활용하였다. 분석 결과, 진로장벽, 성격강점, 진로결정자기효능감, 진로적응성 모두 유의미한 상관관계를 확인하였다. 또 대학생이 지각한 진로장벽과 진로 적응성과의 관계를 성격강점과 진로결정자기효능감이 완전매개하는 것 을 확인하였고 성격강점과 진로결정자기효능감이 순차적으로 매개하는 것을 확인하였다. 즉, 대학생이 지각한 진로장벽으로 인한 어려움을 대 처할 때 자신의 성격강점 인식을 통해 진로결정자기효능감이 향상될 때 진로적응성을 향상시킬 수 있음을 확인하였다. 이를 토대로 대학생 진 로교육과 상담에서 진로적응성 향상을 위한 방안에 대해 논의하였다.
중국 국가 통계국에서 발표한 데이터에 따르면, 2022년 60세 이상 인구는 전체의 19.6%이며, 2035년에는 4억을 초과하여 고령화 사회의 단계에 접어들 것이라고 한다. 질병의 발병률이 매우 높은 고령층은 의약품의 복용 과정에서 주의해야 할 점이 많은 반면, 이에 대한 이해가 부족하여 의약품의 복용에 따른 잠재적인 위험에 항상 노출되어 있다. 이에 따라 의약품 포장에 대한 고령층의 요구를 수용하고, 의약품 복용의 정확성과 편의성을 향상시키는 문제는 당면의 과제가 되고 있다. 본 연구는 디지털 휴먼 기술을 도입하여 의약품 포장의 혁신적인 디자인을 강구하고, 이를 통해 고령층의 의약품 관련 문제에 대한 해결을 목표로 한다. 의약품 포장 디자인에 디지털 휴먼 기술을 적용하는 것은 최근 디지털 발전의 추세에 부합하며, 고령층을 대상으로 하는 의약품 포장 디자인에 새로운 사로를 제공할 수 있다. 따라서 본 연구는 문헌 분석법 및 사례 분석법 등을 통해 고령층을 대상으로 하는 의약품 포장 디자인의 발전 현황을 파악하여, 기존 제한적인 정보만을 제공하던 단일 시각 형태의 전통적인 의약품 포장 디자인의 한계를 극복하고, 새로운 디자인 방안을 제시하여 고령층이 더 다양한 방식으로 의약품 포장을 통해 필요한 정보를 인식할 수 있도록 만들고자 하였다. 기존 의약품 포장 디자인에 대한 분석을 바탕으로 본 연구는 디지털 휴먼 기술과 의약품 포장의 결합에 대한 타당성을 도출했고, 실례를 통해 디지털 휴먼 기술이 의약품 포장에 있어 상당한 응용 가치와 잠재력을 가지고 있다는 사실을 검증하였다.
In 2022, the domestic production performance of functional cosmetics in South Korea reached 4.6 trillion won, accounting for 33.85% of the total cosmetics production. The number of functional cosmetics reviewed increased by about 7.5% from the previous year, totaling 974 items. Especially with the increasing importance of the skin barrier function due to skin sensitivity caused by various environmental pollutants, domestic cosmetic companies are showing interest in the development of new ingredients and products related to this area. This study aims to analyze academic research trends related to in vitro experiments for the development of cosmetics improving the skin barrier, to provide practical information for the cosmetic industry. The findings are as follows: Academic research mainly focused on the efficacy of natural ingredients in improving the skin barrier, but there is a significant lack of quantitative accumulation of research. For the development of skin barrier-improving cosmetic ingredients, efficacy evaluation indicators were set, including hyaluronic acid production, expression of filaggrin gene, loricrin, formation of cornified envelope (CE), and expression of ceramide synthesis enzyme genes. Moreover, effective cosmetic ingredients for improving the skin barrier included lemongrass and perilla leaf extracts, flavonoids, Lactococcus lactis subsp. lactis, Exosomelike Nanovesicles derived from apple callus, Eleutherococcus sessiliflorus, Acanthopanax sessiliflorus, Eleutherococcus gracilistylus, Acer okamotoanum extracts, Aloe vera adventitious root extract, ethanol extract of Aruncus dioicus, and organic solvent fraction of Dracocephalum argunense.
MCCI, one of the ex-vessel phenomena during a severe accident, is generally caused by mutual reactions between molten core and reactor building basemat concrete, but occurs between sacrificial materials made by concrete and corium in APR nuclear power plant with PECS applied. In this paper, MCCI analysis was performed to design and apply a device to block the core melt at the junction connected to the ICI cavity sump from the core catcher installed in the reactor cavity of the APR. Unlike the sacrificial material, which has a cooling effect by inducing erosion of the ex-vessel core melt, the device is composed of concrete applied as a barrier to protect the ICI cavity sump. The decent thickness of the barrier wall of the device was calculated.
컴퓨터 시스템의 성능 및 다양한 전산모사 프로그램의 발전으로 더 복잡한 원소로 이루어진 화학시스템의 해석이 가능해지고, 그에 따라 분자동역학 전사모사를 활용한 연구가 활발히 이루어지고 있다. 특히, 기존에는 실험위주로 진행되던 고분자 막에 대한 기체 투과 특성을 계산하는 연구가 관심을 받고 있고, 식품포장, 의약품등에 사용되고 있는 기체차단성 막 에 대한 분자동역학 연구가 많이 이루어지고 있다. 최근 실크 피브로인을 이용해 코팅막을 만들었을 때 기체 차단 효과가 나 타난다는 보고가 있었고, 본 연구에서는 이러한 실크 피브로인을 활용해 복합막을 만들었을 때 산소 차단 효과가 나타나는지 확인하고자 분자동역학 전산모사를 이용해 연구를 진행하였다. 단일 모델을 제작하고 기체 투과 특성을 계산하고 실험값과 비교를 통해 모델이 실제 실험 결과를 반영하는 것을 확인하였고, 실제 복합막 모델을 만들어 고분자 내에서 기체 이동경로 분석을 진행한 결과 산소 분자가 피브로인 영역을 통과하지 못하고 막히는 것을 보여주었다. 따라서, 실크 피브로인이 도입된 복합막이 산소 차단 성능이 우수하여, 식품포장 등에 유용할 것으로 기대된다.
This study reports an analytical investigation on the development of SB4-grade separated concrete median barriers. The proposed barrier sections comprise three designs, with heights of 810, 1000, and 1270 mm and upper widths of 90, 120, and 120 mm, respectively. Before conducting collision analyses on the proposed sections, the considered collision analysis model was validated using real collision test results; the model was found to accurately predict the real collision test results. The proposed cross-sections were modeled to perform collision analysis according to SB4-grade collision conditions. Results indicated that increasing the cross-section height increased the damaged area and decreased the strength, while the occupant protection performance remained mostly unaffected. Furthermore, the proposed cross-sections met the strength and occupant protection performance criteria specified in domestic guidelines, suggesting their suitability as a separated concrete median barrier for bridges.
Understanding the long-term geochemical evolution of engineered barrier system is crucial for conducting safety assessment in high-level radioactive waste disposal repository. One critical scenario to consider is the intrusion of seawater into the engineered barrier system, which may occur due to global sea level rise. Seawater is characterized by its high ionic strength and abundant dissolved cations, including Na, K, and Mg. When seawater infiltrates an engineered barrier, such dissolved cations displace interlayer cations within the montmorillonite and affect to precipitation/ dissolution of accessory minerals in bentonite buffer. These geochemical reactions change the porewater chemistry of bentonite buffer and influence the reactive transport of radionuclides when it leaked from the canister. In this study, the adaptive process-based total system performance assessment framework (APro), developed by the Korea Atomic Energy Research Institute, was utilized to simulate the geochemical evolution of engineered barrier system resulting from seawater intrusion. Here, the APro simulated the geochemical evolution in bentonite porewater and mineral composition by considering various geochemical reactions such as mineral precipitation/dissolution, temperature, redox processes, cation exchange, and surface complexation mechanisms. The simulation results showed that the seawater intrusion led to the dissolution of gypsum and partial precipitation of calcite, dolomite, and siderite within the engineered barrier system. Additionally, the composition of interlayer cation in montmorillonite was changed, with an increase in Na, K, and Mg and a decrease in Ca, because the concentrations of Na, K, and Mg in seawater were 2-10 times higher than those in the initial bentonite porewater. Further studies will evaluate the geochemical sorption and transport of leaked uranium-238 and iodine-129 by applying TDB-based sorption model.
Copper, mainly used as a material for outer canister, generates various corrosion products under aerobic and anaerobic conditions in the operational and/or post-closure phases of the deep geological repository. These products could affect performance of engineering barrier system (EBS) through interaction with surrounding bentonite that makes up the buffer and backfill materials. Accordingly, in this study, we suggested research items to be conducted to minimize degradation of EBS due to copper corrosion products, based on the phenomenological review results for copper corrosion mechanisms and interaction between resultant product and bentonite in the deep geological disposal environment. During the post-closure phase, condition in the disposal facility changes form aerobic to anaerobic over time, and thereby, causes and products of copper corrosion vary. Under aerobic condition, copper corrosion is mainly induced by oxygen (O2) in the repository, chloride (Cl-) and carbonate (CO3 2-) ions from groundwater flowing into the facility, resulting in corrosion products such as cuprite (Cu2O), tenorite (CuO), atacamite (CuCl2·3Cu(OH)2) and malachite (Cu2CO3(OH)2). And, copper corrosion under anaerobic condition is primarily due to hydrogen sulfide (H2S) and sulfate (SO4 2-) in groundwater flowing into the facility, leading to formation of chalcocite (Cu2S) and covellite (CuS) as corrosion products. Depending on environment of the disposal facility, copper corrosion products are dissolved and ionized to Cu2+ in groundwater, and subsequently adsorbed on the nearby smectite. Then, it causes a cation exchange reaction with exchangeable cations in the interlayer of smectite. As a result of reviewing the previous experiments, it was confirmed that Cu2+-exchanged bentonite has a slightly reduced basal spacing and swelling capacity. From the results as above, there is a possibility that performance of EBS may be degraded due to copper corrosion products. To minimize its effect of degradation in the domestic facility, items to be further studied are as follows: (a) Method for reducing copper corrosion such as selection of appropriate material and structure for the canister, and (b) How to control dissolution of copper canister product into groundwater through predicting type and ionization process. The results of this study could be directly used to developing design concept of EBS for the domestic disposal facility and to establishing roadmap of future R&D programs.
The effectiveness of a crystalline natural barrier in providing sealing capabilities is based on the behavior of numerous fractures and their intersections within the rock mass. It is important to evaluate the evolving characteristics of fractured rock, as the hydro-mechanical coupled processes occurring through these fractures play a dominant role. KAERI is actively developing a true tri-axial compression test system and concurrently conducting hydro-mechanical experiments using replicated fractured rock samples. This research is focused on a comprehensive examination of coupled processes within fractures, with a particular emphasis on the development of true tri-axial testing equipment. The designed test system has the capability to account for three-dimensional stress conditions, including vertical and both maximum and minimum horizontal principal stresses, realizing the disposal conditions at specific underground depths. Notably, the KAERI-designed test system employs the mixed true tri-axial concept, also known as the Mogi-type, which allows for fluid flow into fractures under tri-axial compression conditions. This system utilizes a hydraulic chamber to maintain constant stress in one direction through the application of oil pressure, while the other two directional stresses are applied using rigid platens with varying magnitudes. Once these mechanical stress conditions are established, control over fluid flow is achieved through the rigid platens in contact with the specimen section. This pioneering approach effectively replicates in-situ mechanical conditions while concurrently observing the internal fluid flow patterns within fractures, thereby enhancing our capacity to study these coupled phenomena. As future research, numerical modeling efforts will be proceeding with experimental data-driven approaches to simulate the coupled behavior within the fractures. In these numerical studies, two distinct fracture geometry domains will be generated, one employing simplified rough-walled fractures and the other utilizing mismatched rough-walled fractures. These investigations mark the preliminary steps in the process of selecting and validating an appropriate numerical model for understanding the hydro-mechanical evolution within fractures.
The engineered barrier system (EBS), composed of spent nuclear fuel, canister, buffer and backfill material, and near-field rock, plays a crucial role in the deep geological repository for high-level radioactive waste. Understanding the interactions between components in a thermo-hydro-mechanical -chemical (THMC) environment is necessary for ensuring the long-term performance of a disposal facility. Alongside the research project at KAERI, a comprehensive experimental facility has been established to elucidate the comprehensive performance of EBS components. The EBS performance demonstration laboratory, which installed in a 1,000 m2, consists of nine experimental modules pertaining to rock mechanics, gas migration, THMC characteristics, buffer-rock interaction, buffer & backfill development, canister corrosion, canister welding, canister performance, and structure monitoring & diagnostics. This facility is still conducting research on the engineering properties and complex interactions of EBS components under coupled THMC condition. It is expected to serve as an important laboratory for the development of the key technologies for assessing the long-term stability of engineered barriers
In order to ensure the long-term safety of a deep geological repository, the performance assessment of the Engineered Barrier System (EBS) considering a thermal process should be performed. The maximum temperature at the side wall of a disposal canister for the technical design requirement should not exceed 100°C. In this study, the thermal modelling was conducted to analyze the effects of the thermal process from a disposal canister to the surrounding near-field host rock using the PFLOTRAN code. The mesh was generated using the LaGriT code and the material properties were assigned by applying the FracMan code. Initial conditions were set as the average geothermal gradient (25.7°C/km) and an average surface temperature (14.7°C) in Korea. The highest temperature was observed at the middle of the canister side wall. The temperature of the buffer was lower than that of the canister, and the temperature increase of the deposition tunnel and the host rock was insignificant due to the lower effect of the heat source. The result of the thermal evolution of the EBS represented the highest thermal effects in the vicinity of the canister. In addition, the thermal effects were largely decreased after 10 years of the entire simulation period. It demonstrated that the model took 3 years to heat up the buffer around the canister. The temperature at the canister side wall increased until 3 years and then decreased after that time. This is because that the radioactive decay heat from the heat source was emitted enough to raise the overall temperature of the EBS by 3 years. However, the decay heat rate of the canister decreased exponentially with the disposal time and then its decay heat was not emitted enough after 3 years. In conclusion, the peak temperature results of the EBS were lower than 70°C to meet the technical design requirement.
The natural barrier system surrounding the geological repository for high-level radioactive waste plays a crucial role in preventing or delaying the leakage of radionuclides. Therefore, the natural barrier should ensure low permeability to prevent groundwater flow into the engineered barrier system throughout the repository’s lifetime. Crystalline rock, considered as the host rock for the geological repository in Korea, exhibits low intact rock permeability, but the crystalline rock often contains the multiple discontinuities due to its high brittleness that can allow the unexpected fluid flow. Therefore, the long-term hydraulic behavior of the discontinuity should be characterized while considering additional thermal, mechanical, and chemical effects. In comparison to thermal, hydraulic, and mechanical processes, the chemical processes on the discontinuities progress relatively slowly, resulting in limited researches to include these chemical processes. This research introduces mechanisms the involving coupled thermal-hydraulic-mechanicalchemical processes focusing on the rough fracture surfaces and asperities. The chemically-induced changes in mechanical and hydraulic properties are described based on pressure solution and precipitation concepts. A comprehensive review of laboratory tests, field tests, and numerical simulations is conducted related to the chemically-induced coupled processes in fractured rock. Laboratory tests, in particular, concentrate on microscopic changes in fracture asperities induced by pressure solution to analyze chemically-induced aperture changes. The TOUGHREACT, an integral finite difference method program for thermal-hydraulic-chemical simulations, is generally employed to model the chemical response of pressure solution and precipitation on fracture surfaces. The TOUGHREACT includes a module to describe effective porosity and permeability changes based on the modified cubic law, so the real-time change of the fracture permeability can be reflected during the flow simulation. Considering the coupled thermal-hydraulic-mechanicalchemical processes of discontinuity, it becomes evident that the chemical processes under repository conditions (long-term, high temperature, and high pressure) can disturb the hydraulic performance of the natural barrier, so further research is required to characterize the chemically-induced coupled processes for assessing the long-term performance of the natural barrier system.
In this study, a third metal layer with a higher corrosion potential than copper was introduced between the copper and cast iron layer to strengthen the corrosion resistance of the copper layer which is considered as a corrosion resistant barrier in the disposal container for spent nuclear fuel. Three types of corrosion-resistant metals, silver, nickel, and titanium, were selected as the intermediate insertion layer, and the galvanic specimens of two bonded metals were exposed to KURT (KAERI Underground Research Tunnel) groundwater and a high voltage of 1.0 V was applied to corrode the specimens at electrochemically accelerated condition. Corrosion of copper part was confirmed in Cu-Ti, Cu-Ni, and Cu-Ag galvanic specimens, but copper part was not corroded in Cu-Fe galvanic specimen. If the corrosion-resistant intermediate layer proposed in this study works properly, the local corrosion problem of copper disposal canister is expected to be some degree solved, which can apply to a welding part or a stress concentrated part.
The WRK (Waste Repository Korea bentonite) compacted bentonite medium has been considered as the appropriate buffer material in the Korean SNF (Spent nuclear fuel) repository site. In this study, hydraulic properties of the WRK compacted bentonite core (4.5 cm in diameter and 1.0 cm in length) as the buffer material were investigated in laboratory experiments. The porosity and the entry pressure of the water saturated core at different confining pressure conditions were measured. The average velocity of water flow in the WRK compacted bentonite core was calculated from results of the breakthrough curves of the CsI aqueous solution and the hydraulic conductivity of the core was also calculated from the continuous flow core experiments. Because various gases could be generated by continuous SNF fission, container corrosion and biochemical reactions in the repository site, the gas migration property in the WRK compacted bentonite core was also investigated in experiments. The gas permeability and the average of gas (H2) in the core at different water saturation conditions were measured. Laboratory experiments with the WRK Compacted bentonite core were performed under conditions simulating the DGR environment (confining pressure: 1.5- 20.0 MPa, injection pressure: 1.0-5.0 MPa, water saturation: 0-100%). The WRK Compacted bentonite core was saturated at various confining pressure conditions and the porosity ranged from 27.5% to 43.75% (average: 36.75%). The calculated hydraulic conductivity (K) of the core using experimental results was 8.69×10-11 cm/s. The gas permeability of the core when the water saturation 0~58 % was ranged of 19.81~3.43×10-16 m2, representing that the gas migration in the buffer depends directly on the water saturation degree of the buffer medium. The average gas velocity in the core at 58% of water saturation was 9.8×10-6 m/s, suggesting that the gas could migrate fast through the buffer medium in the SNF repository site. Identification of the hydraulic property for the buffer medium, acquired through these experimental measurements is very rare and is considered to have high academic values. Experimental results from this study were used as input parameter values for the numerical modeling to simulate the long-term gas migration in the buffer zone and to evaluate the feasibility of the buffer material, controlling the radionuclide-gas migration in the SNF repository site.
호장은 마디풀과에 속하는 다년초로 우리나라를 포함한 동아시아에서 잘 자생한다. 호장근은 호장의 뿌리로 항염증과 진경제로 사용되어 왔으며 유효성분으로 emodin을 포함하고 있다. 피부의 표피는 자극, 해로운 물질을 차단하고 수분 증발을 방지함으로써 체내를 보호하는 중요한 역할을 한다. 본 연구에 서는 호장근과 그 유효성분인 emodin이 피부 장벽과 보습능에 미치는 영향에 대해 평가하고자 하였다. 먼 저 호장근은 ABTS+ radicals을 우수하게 제거함으로써 항산화 효능이 뛰어남을 확인하였다. 다음으로, 실 시간 중합연쇄효소반응을 통해 각질형성세포의 분화에 중요한 역할을 하는 filaggrin의 유전자 발현을 비교 한 결과, 호장근과 emodin에 의해 농도-의존적으로 filaggrin mRNA 발현이 증가하였다. 또한, 호장근과 emodin은 히알루론산 합성에 중요한 역할을 하는 HAS-2 mRNA 발현을 유의하게 증가시키는 것으로 나 타났다. 종합적으로, emodin을 유효성분으로 포함하는 호장근은 피부 장벽 강화와 보습능 증강을 위한 기 능성 화장품 소재로서 활용될 수 있을 것으로 기대된다.