• Nuclear Engineering and Technology
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• 제53권10호
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• pp.3359-3366
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• 2021

An engineered barrier system (EBS) for the deep geological disposal of high-level radioactive waste (HLW) is composed of a disposal canister, buffer material, gap-filling material, and backfill material. As the buffer fills the empty space between the disposal canisters and the near-field rock mass, heat energy from the canisters is released to the surrounding buffer material. It is vital that this heat energy is rapidly dissipated to the near-field rock mass, and thus the thermal conductivity of the buffer is a key parameter to consider when evaluating the safety of the overall disposal system. Therefore, to take into consideration the sizeable amount of heat being released from such canisters, this study investigated the thermal conductivity of Korean compacted bentonites and its variation within a temperature range of 25 ℃ to 80-90 ℃. As a result, thermal conductivity increased by 5-20% as the temperature increased. Furthermore, temperature had a greater effect under higher degrees of saturation and a lower impact under higher dry densities. This study also conducted a regression analysis with 147 sets of data to estimate the thermal conductivity of the compacted bentonite considering the initial dry density, water content, and variations in temperature. Furthermore, the Kriging method was adopted to establish an uncertainty metamodel of thermal conductivity to verify the regression model. The R² value of the regression model was 0.925, and the regression model and metamodel showed similar results.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1511-1518
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• 2021

In most countries, the thermal criteria for the engineered barrier system (EBS) is set to below 100 ℃ due to the possible illitization in the buffer, which will likely be detrimental to the performance and safety of the repository. On the other hand, if the thermal criteria for the EBS increases, the disposal density and the cost-effectiveness for the high-level radioactive wastes will dramatically increase. Thus, fundamentals on the thermal behavior of the buffer under the elevated temperatures is of crucial importance. Yet, the behaviors at the elevated temperatures of the bentonite under groundwater-saturated conditions have not been reported to-date. Here, we have developed an in-situ synchrotron-based method for the thermal behavior study of the buffer under the elevated temperatures (25-250 ℃), investigated dspacings of the montmorillonite in the Korean bentonite (i.e., Ca-type) at dry and KURT (KAERI Underground Research Tunnel) groundwater-saturated conditions (KJ-ii-dry and KJ-ii-wet), and compared the behaviors with that of MX-80 (i.e., Na-type, MX-80-wet). The hydration states analyzed show tri-, bi-, and mono-hydrated at 25, 120, and 250 ℃, respectively for KJ-ii-wet, whereas tri-, mono-, and de-hydrated at 25, 150, and 250 ℃, respectively for MX-80-wet. The Korean bentonite starts losing the interlayered water at lower temperatures; however, holds them better at higher temperatures as compared with MX-80.

• 방사성폐기물학회지
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• 제19권4호
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• pp.469-477
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• 2021

Safe storage of spent nuclear fuel in deep underground repositories necessitates an understanding of the long-term alteration of metal canisters and buffer materials. A small-scale laboratory alteration test was performed on metal (Cu or Fe) chips embedded in compacted bentonite blocks placed in anaerobic water for 1 year. Lactate, sulfate, and bacteria were separately added to the water to promote biochemical reactions in the system. The bentonite blocks immersed in the water were dismantled after 1 year, showing that their alteration was insignificant. However, the Cu chip exhibited some microscopic etch pits on its surface, wherein a slight sulfur component was detected. Overall, the Fe chip was more corroded than the Cu chip under the same conditions. The secondary phase of the Fe chip was locally found as carbonate materials, such as siderite (FeCO₃) and calcite ((Ca, Fe)CO₃). These secondary products can imply that the local carbonate occurrence on the Fe chip may be initiated and developed by an evolution (alteration) of bentonite and a diffusive provision of biogenic CO₂ gas. These laboratory scale results suggest that the actual long-term alteration of metal canisters/bentonite blocks in the engineered barrier could be possible by microbial activities.

• 방사성폐기물학회지
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• 제22권2호
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• pp.185-199
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• 2024

Disposal cover as an engineered barrier of a near-surface disposal facility for low and very low-level radioactive waste is composed of a multi-layer to isolate radioactive waste from environmental influences for the long term. To acquire a realistic forecast for the post-closure period of the disposal facility, it is essential to carry out long-term experimental research in a similar condition to the actual disposal environment. Hence, a performance test facility of the disposal cover was constructed in Gyeongju low and intermediate level radioactive waste disposal center in 2022. The constructed performance test facility has differences from the material properties presented in the design. These differences are factors that affect the prevent rainfall infiltration, which is one of the important roles of the disposal cover. Therefore, in this study, a numerical simulation of rainfall infiltration into the performance test facility was performed for the designed case and the actual constructed case. To simulate the behavior of water infiltration, the FEFLOW software based on the finite element method is used. Through the analysis of numerical simulation results, it is confirmed that the hydraulic conductivity of the material constituting the multi-layer of the disposal cover greatly influences the amount of water infiltration.

• 방사성폐기물학회지
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• 제22권1호
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• pp.9-16
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• 2024

The bentonite buffer material is a crucial component in an engineered barrier system used for the disposal of high-level radioactive waste. Because a large amount of heat from the disposal canister is released into the bentonite buffer material, the thermal conductivity of the bentonite buffer is a crucial parameter that determines the design temperature. At the Korea Atomic Energy Research Institute (KAERI), a new standard bentonite (Bentonil-WRK) has been used since 2022 because Gyeongju (KJ) bentonite is no longer produced. However, the currently available data are insufficient, making it essential to investigate both the basic and complex properties of Bentonil-WRK. Thus, this study evaluated its geotechnical and thermal properties and developed a thermal conductivity empirical model that considers its dry density, water content, and temperature variations from room temperature to 90℃. The coefficient of determination (R²) for the model was found to be 0.986. The thermal conductivity values of Bentonil-WRK were 1-10% lower than those of KJ bentonite and 10-40% higher than those of MX-80 bentonites, which were attributable to mineral-composition differences. The thermal conductivity of Bentonil-WRK ranged between 0.504 and 1.149 W·(m^-1·K^-1), while the specific heat capacity varied from 0.826 to 1.138 (kJ·(kg^-1·K^-1)).

• 한국진공학회:학술대회논문집
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• 한국진공학회 2011년도 제40회 동계학술대회 초록집
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• pp.134-134
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• 2011

High-k dielectric materials such as $HfO_2$, $ZrO_2$ and $Al_2O_3$ increase gate capacitance and reduce gate leakage current in MOSFET structures. This behavior suggests that high-k materials will be promise candidates to substitute as a tunnel barrier. Furthermore, stack structure of low-k and high-k tunnel barrier named variable oxide thickness (VARIOT) is more efficient.[1] In this study, we fabricated the $WSi_2$ nanocrystals nonvolatile memory device with $SiO_2/HfO_2/Al_2O_3$ tunnel layer. The $WSi_2$ nano-floating gate capacitors were fabricated on p-type Si (100) wafers. After wafer cleaning, the phosphorus in-situ doped poly-Si layer with a thickness of 100 nm was deposited on isolated active region to confine source and drain. Then, on the gate region defined by using reactive ion etching, the barrier engineered multi-stack tunnel layers of $SiO_2/HfO_2/Al_2O_3$ (2 nm/1 nm/3 nm) were deposited the gate region on Si substrate by using atomic layer deposition. To fabricate $WSi_2$ nanocrystals, the ultrathin $WSi_2$ film with a thickness of 3-4 nm was deposited on the multi-stack tunnel layer by using direct current magnetron sputtering system [2]. Subsequently, the first post annealing process was carried out at $900^{\circ}C$ for 1 min by using rapid thermal annealing system in nitrogen gas ambient. The 15-nm-thick $SiO_2$ control layer was deposited by using ultra-high vacuum magnetron sputtering. For $SiO_2$ layer density, the second post annealing process was carried out at $900^{\circ}C$ for 30 seconds by using rapid thermal annealing system in nitrogen gas ambient. The aluminum gate electrodes of 200-nm thickness were formed by thermal evaporation. The electrical properties of devices were measured by using a HP 4156A precision semiconductor parameter analyzer with HP 41501A pulse generator, an Agillent 81104A 80MHz pulse/pattern generator and an Agillent E5250A low leakage switch mainframe. We will discuss the electrical properties for application next generation non-volatile memory device.

• Journal of Pharmaceutical Investigation
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• 제33권2호
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• pp.145-149
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• 2003

Manufacturing facilities of the pharmaceuticals must meet certain level of the cleanness required so that foreign substances such as dust, moisture, heat, microorganism, or virus do not contaminate the product. In case of radiopharmaceuticals for medical treatment and diagnosis, not only should the operators and environment be protected from radiation but also need to be isolated from the foreign contaminant. Therefore, manufacturing facilities for radiopharmaceuticals must satisfy the design standards of both hot cell and clean room which are specified by GMP. However, standards of maintaining negative pressure for preventing spread of radioactive contaminant in isolated facilities conflict with the standards of maintaining positive pressure for keeping cleanness. To solve this problem, air pressure of hot cell was designed lower than in the adjacent area to meet standards of the radiation safety. To keep higher cleanness in certain part of the hot cell for filling, minimal relative positive pressure allows. In order to effectively maintain the cleanness that is required for production of Tc-99m generator, which takes 70% of whole demand of radiopharmaceuticals, the rooms placed in each side of production room are used as a buffer area and three lead hot cells are installed in production room. In this research, we established the appropriate engineered design concept for Tc-99m generator manufacturing facility, which satisfies both GMP cleanness standard for preventing particles, bacteria, other contaminants and the regulations of radiation safety for supervising and controlling the amount of radiation exposure and exhausted radioactivity. And the concept of multi-barrier buffer zones is introduced to apply negative air pressure for hot cell with first priority and to continue relative positive air pressure for clean room.

• Journal of Pharmaceutical Investigation
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• 제29권2호
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• pp.87-92
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• 1999

Drug delivery to the brain may be achieved by producing chimeric peptide, attaching the drug to protein 'vectors' which are transported into the brain from the blood by a receptor-mediated transcytosis through the blood-brain barrier (BBB). Since the BBB expresses high concentrations of transferrin receptor, and it was reported that anti-transferrin receptor mouse monoclonal antibody (OX26) undergoes transcytosis through the BBB, it is logical to assume that a drug delivery system via transferrin receptor-mediated transcytosis is a promising strategy. In the present study, therefore, we tested feasibility of several OX26 based vectors for the brain delivery of a model drug. Avidin-based delivery vectors such as OX26-streptavidin (OX26-SA), OX26-neutralite avidin (OX26-NLA) were chemically synthesized vectors and OX26 immunoglobulin G 3 type $C_{H}3$ fusion avidin $(OX26\;IgG3C_H3-AV)$ was genetically engineered. To improve the efficiency of producing chimeric peptide, we used avidin-biotin technology. Pharmacokinetics of $[^3H]biotin$ bound to OX26-SA, OX26-NLA and $OX26\;IgG3C_H3-AV$ was determined by intravenous injection technique, and their stabilities in plasma were analyzed using HPLC. The brain delivery of $[^3H]biotin$ bound to OX26-SA, OX26-NLA and OX26\;$IgG3C_{H}3-AV$ (expressed as %ID/g brain) was $0.22{\pm}0.01$, $0.18{\pm}0.01$ and $0.25{\pm}0.09$, respectively. The areas under the plasma concentration versus time curve (AUC) for OX26-SA, OX26-NLA, $OX26\;IgG3C_H3-AV$ from time zero to 60 min were $209{\pm}10$, $195{\pm}9$, $134{\pm}29\;%ID\;min/ml$ respectively and their total clearances $(CL_{tot})$ were $1.00{\pm}0.09$, $1.08{\pm}0.07$ and $1.54{\pm}0.29\;ml/min/kg$, espectively. These results showed that these vectors possess preferable pharmaceutical (e.g., resonable stability) and pharmacokinetics (e.g., significant brain uptake and enhanced AUC) for brain delivery. Therefore, these vectors may be broadly useful in the brain delivery of drugs that are not transported into the brain to a significant extent.

• 지질공학
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• 제7권3호
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• pp.229-245
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• 1997

대규모의 암반 공동을 이용하는 대표적 시설이 지하유류비축시설과 방사성폐기물처분시설은, 공히 암반이 갖는 천연적인 방벽기능과 안정성 확보를 위한 보장 조치로서 인공방벽시설을 설치한다느 공통점이 있다. 지하유류비축시설의 설계,건설 및 운영의 각 단계에서 모암에 분포한는 지질구조와 그들의 수리학적 특성이 시설이 안전성 및 성능에 가장 중요한 역할을 한다. 시설 설치가 가능한 규모의 암반 block 내에 분포된 단열체제는 고유의 기하학적 특성과 수리적 특성이 혼재되어 복합적인 수리체계를 형성하고 있기 때문에 이에 대한 정확하고 정량적인 조사.평가가 지하비축시설의 수리적 안정성을 좌우하게 된다. 본 논문은 지하유류비축시설의 성능평가에서 요구되는 자연방벽의 수밀성 기능을 평가하기 위하여 지하문체계의 해석과정에서 고려되어야 할 문제점들을 우선 검토하고, 시설의 안전한 운영을 위하여 다루어져야 할 수리 안정성관련 파라메테에 대한 조사 및 평가방법을 다룬다.

• 터널과지하공간
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• 제21권4호
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• pp.264-273
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• 2011

고준위폐기물처분장에서 벤토나이트완충재는 공학적방벽의 중요한 구성요소 중 하나이다. 벤토나이트완충재는 방사성폐기물로부터의 붕괴열, 주위 암반으로부터의 지하수 유입, 고밀도로 압축된 벤토나이트 자체의 높은 팽윤압에 의해 큰 영향을 받는다. 그러므로 벤토나이트완충재의 열-수리-역학적 특성 이해와 평가모델의 입력데이터 확보는 고준위폐기물처분장의 성능 및 안전성 평가를 위해서 선행되어야 할 중요한 과제이다. 본 논문에서는 우리나라 고준위폐기물처분장 완충재 후보물질을 대상으로 지금까지 수행된 열-수리-역학적 특성을 분석하고, 기준벤토나이트완충재 조건을 설정하여, 이 조건에 부합되는 벤토나이트완충재의 열-수리-역학적 특성치를 제시하였다.