In this study, the following results were obtained by designing a high-efficiency hydrogel and colloid fusion applicator and checking production speed(hydrogel) and working setting time(coating time) by promoting the starting product. As a result of performing a product production test by manufacturing a starting product based on the process automation design, the production volume increased by about three times from 4m per minute to an average of 11m per minute. The working setting time(coating time) of the fusion applicator was shortened from the target of 10minutes to 1.69minutes, which had the effect of reducing the loss of work time.

The main noise of a large machine can be divided into the noise generated during the work process and the noise of the equipment used in the work. The main noise in the noisy area is the air propagation sound caused by the operation of the rotating body. This is not fixed, but changes depending on the situation at the time of measurement. Workplaces exposed to noise can harm workers' health and cause related industrial disasters, resulting in many complaints and social problems, and eventually lead to a lot of damage in terms of productivity. Large machines that need noise reduction the most are motors, pumps, fans, blowers, and compressors. To reduce noise, mechanical structure or material changes are most effective. In this study, the noise reduction method and noise management method of large machines were investigated. To measure noise, the same method as ISO 3744 in Europe and JISA 8305 in Japan was used as KS A ISO 3744, KS A ISO 3746, which is a method of measuring the acoustic power level of machinery.

Due to the development of the industry, the machinery of plant facilities becomes large and operates at high speed and high power. Workers at plant facility sites are exposed to high noise and impact noise, and the number of people with noise-induced hearing loss is increasing every year. Therefore, in order to minimize such damage, many efforts have been made to reduce the noise of large machines in production facilities. Measures, education, and recommendation of wearing hearing protectors are needed to protect the hearing of workers in high noise industries. In addition, it is urgent to reduce noise sources by blocking noise propagation paths, such as installing noise boxes and silencers, and installing facilities and equipment that generate less noise. It is necessary to repair the noise reduction device of the large machine of the plant or to study the noise reduction device when designing the plant.

본 연구는 기업의 중간관리자, 코칭역량 척도(CCSMM)의 신뢰도와 타당도를 검증하는데 목적이 있다. 타당화 연구를 위한 중간관리자의 코칭역량 척도의 문항 구성요인은 목표달 성, 커뮤니케이션, 대인관계, 자기주도의 4개 영역과 목표정하기, 목표달성, 경 청, 질문, 피드백, 상호존중 및 신뢰, 지지 및 지원, 자기효능감 및 성장/미래지향 성의 9개 요인 40문항으로 구성되어 있다. 상기와 같이 새롭게 개발된 중간관리자의 코칭역량 척도의 일반화를 위해 타 당도의 증거를 제시하고자, 기존의 타당화된 검사 도구와의 상관계수를 확인하 였다. 상관관계 분석결과 중간관리자의 코칭역량 척도와 Stowell(1986)의 코칭 리더십 척도 간에 높은 유의미한 정적상관을 보였다. 즉, 목표정하기, 목표달성, 경청, 질문, 피드백, 상호존중 및 신뢰, 지지 및 지원, 자기효능감, 성장/미래지향 성 등 중간관리자의 코칭역량 구성요인과 코칭리더십 척도 간에 모두 유의미한 정적상관이 있다는 것이 밝혀졌다. 결론적으로 본 연구는 기업의 중간관리자, 코칭역량 척도의 신뢰도와 타당도 의 타당화 검증을 통해 기업에 근무하는 중간관리자들의 코칭역량 향상에 기여 할 수 있는 계기가 되었다는 데 의의가 있다.

Decommissioning waste is generated at all stages during the decommissioning of nuclear facilities, and various types of radioactive waste are generated in large quantities within a short period. Concrete is a major building material for nuclear facilities. It is mixed with aggregate, sand, and cement with water by the relevant mixing ratio and dried for a certain period. Currently, the proposed treatment method for volume reduction of radioactive concrete waste was involved thermomechanical and chemical treatment sequentially. The aggregate as non-radioactive materials is separated from cement components as contaminated sources of radionuclides. However, to commercialize the process established in the laboratory, it is necessary to evaluate the scale-up potential by using the unit equipment. In this study, bench-scale testing was performed to evaluate the scale-up properties of the thermomechanical and chemical treatment process, which consisted of three stages (1: Thermomechanical treatment, 2: Chemical treatment, 3: Wastewater treatment). In the first stage, lab, bench, and pilot scale thermomechanical tests were performed to evaluate the treated coarse aggregate and fines. In the second stage, the fine particles generated by the thermomechanical treatment process, were chemically treated using dissolution equipment, after then the removal efficiency and residual of cement in the small aggregate was compared with laboratory results. The final stage, the secondary wastewater containing contaminant nuclides was treated, and the contaminant nuclides could be removed by chemical precipitation method in the scale-up reactors. Furthermore, an additional study was required on the solid-liquid separation, which connected each part of the equipment. It was conducted to optimize the separation method for the characteristics of the particles to be separated and the purpose of separation. Therefore, it is expected that the basic engineering data for commercialization was collected by this study.

Regulations on the concentration of boron discharged from industrial facilities, including nuclear power plants, are increasingly being strengthened worldwide. Since boron exists as boric acid at pH 7 or lower, it is very difficult to remove it in the existing LRS (Liquid Radwaste System) using RO and ion exchange resin. As an alternative technology for removing boron emitted from nuclear power plants, the electrochemical boron removal technology, which has been experimentally applied at the Ringhal Power Plant in Sweden, was introduced in the last presentation. In this study, the internal structure of the electrochemical module was improved to reduce the boron concentration to 5 mg/L or less in the 50 mg/L level of boron-containing waste liquid. In addition, the applicability of the electrochemical boron removal technology was evaluated by increasing the capacity of the unit module to 1 m3/hr in consideration of the actual capacity of the monitor tank of the nuclear power plant. By applying various experimental conditions such as flow rate and pressure, the optimum boron removal conditions using electrochemical technology were confirmed, and various operating conditions necessary for actual operation were established by configuring a concentrated water recirculation system to minimize secondary waste generation. The optimal arrangement method of the 1 m3/hr unit module developed in this study was reviewed by performing mathematical modeling based on the actual capacity of monitor tank and discharge characteristics of nuclear power plant.

In high-level radioactive waste disposal, a high temperature is generated from the canister containing the waste in the engineered barrier, while groundwater flows into the buffer system from the host rock. The temperature increase and groundwater inflow result in the water phase change and saturation variation. Saturation change is related to the thermal conductivity of buffer material; hence the phase change and saturation strongly interact with the temperature evolution. The complex coupled behavior affects the stability of the whole disposal system, and the security of the repository is critical to human-being life. However, it is difficult to predict the long-term coupled behavior in the disposal system due to the considerable field-test scale, and therefore a numerical simulation is a suitable method having repeatability and cost-effectiveness. DECOVALEX is an international cooperating project for developing numerical methods and models for thermo-hydro-mechanical-chemical (THMC) interaction. DECOVALEX has a four-year cycle with various topics. At the current phase, Task C aims to simulate the full-scale emplacement (FE) experiment performed at Mont Terri underground rock laboratory. Nine research groups are participating in the task, and among them, KAERI simulates the experiment using OGS-FLAC. The simulator combines OpenGeoSys for TH simulation and FLAC3D for M simulation. Through the benchmark simulation, we verified OGS-FLAC for the two-phase flow analysis in the disposal system and finally modeled the FE experiment with a three-dimensional grid. We performed a simple sensitivity analysis to investigate the effect of input parameters on the two-phase flow system and confirmed that the compressibility and permeability affected the flow behavior. We also compared the simulation results to the field data and obtained well-matched results from a series of simulation.

According to the ‘Basic Plan for High-Level Radioactive Waste Management (draft)’, the total amount of CANDU spent nuclear fuel is expected to be approximately 660,000 bundles. To safely and efficiently transport this amount to interim storage facilities, it is essential to develop a large-capacity transport cask. Therefore, we have been developing a large-capacity PHWR spent nuclear fuel transport cask, called the KTC-360 transport cask. According to the transport-cask related regulations, the KTC-360 transport cask was classified as a Type B package, and such packages must be able to withstand a temperature of 800°C for a period of 30 min. It is desirable to conduct a test using a fullscale model of a shipping package when performing tests to evaluate its integrity. However, it is costly to perform a test using a full-scale model. Therefore, to evaluate the thermal integrity of the KTC-360 transport cask, the fire test was conducted using a slice model. For comparison purposes, the fire test was also carried out using a 1/4 scale model. In the fire test using a slice model and in the fire test using a 1/4 scale model, the maximum temperature of the cask body was lower than the permitted maximum temperature limit. Therefore, the thermal integrity of the KTC-360 transport cask could be considered to be maintained. The temperature results from the fire test using a slice model were higher than those of the fire test using a 1/4 scale model. Therefore, the effect of flame on a transport cask without combustible materials, such as the KTC-360 transport cask, seems to be affected by the reduction in the time rather than the size reduction.

The management before disposal of spent nuclear fuel is an essential process for safe management. It is important to determine the amount of nuclide inventory in order to ensure the integrity of spent nuclear fuel, as radiation generated from the nuclides is generated along with residual heat in the spent nuclear fuel. Based on the data on the characteristics of spent nuclear fuel generated in Korea, the correlation equation between burnup and enrichment was derived by referring to overseas cases (Sweden). Source term analysis was performed using the SCALE ORIGEN ARP code by securing the burnup history of nuclear fuel. Calculation was performed by inputting the combustion history of the fuel WH14×14 and WH17×17 as a reference for CE16×16 spent fuel. Through this study, the relationship was identified using the burnup, enrichment, and cooling time factors that influence the characteristics of spent nuclear fuel. In addition, the total source and spectrum data from neutrons and gamma sources were used to find out the characteristics of fuel.

Despite the massive impact of COVID-19 on society, beyond the numbers of confirmed cases and deaths, there remains a lack of large-scale data depicting the effects of the virus on the society of the Republic of Korea. To fill this gap, we collected 1.822 million news articles with more than 1 billion morphemes from January 2020 to June 2022, creating a Korean version of the Coronavirus Corpus. This corpus is introduced in the current study. In addition, to demonstrate how such massive corpus can be utilized, we conducted information theoretical analyses to see how the stance of the press media on topics such as vaccines and social distancing affected the COVID-19 situation in the Republic of Korea. Specifically, we utilized several computational linguistic skills including concordance building and sentiment analysis through both traditional and machine learning techniques and measured the transfer entropy to estimate the impact with information theory. The results suggest that the overall impact of the press media on the society was minimal to non-existent.

Enhancing income for small-scale farmers in developing countries, is one of the major concerns for governments and many stakeholders. This is attributed by the fact that, a majority of smallscale farmers in the region are characterized by low income earners caused by agronomic related challenges, such as low productivity of input factors. In addressing this challenge, the purpose of this study was to assess the impact of outgrower scheme on its members’ income, using the propensity score matching approach. Through this approach the study assessed cross-sectional data, collected from small-scale tea farmers in the Mufindi district, founded in Tanzania. Results of the assessment on the impact of outgrower scheme on its members, suggest that the scheme has a negative and insignificant impact on its members’ income. This implies that, the outgrower scheme does not meet its intended objective of raising the income of its members, due to failure of improving quality as well as quantity of tea produced in the study area.

ROK Navy intends to secure the Korean-type aircraft carrier in order to effectively prepare for various future security threats. In general, the Korean national competency is considered to be at the level of having an aircraft carrier, but it is unclear what scale aircraft carrier would be appropriate. In this study, the efficiency was evaluated through the relative comparison between national competency(national power, economic power) and the scale of aircraft carriers, and the optimal scale of the Korean-type aircraft carrier that could be acquired was presented. A DEA(Data Envelopment Analysis) model was applied to aircraft carriers(19 aircraft carriers in 11 countries) currently in operation and scheduled to be possessed in the world. As input variables, CINC(Composite Index of National Capability) and GDP(Gross Domestic Product), which are the most widely used as indicators of national and economic power, and as output variables, the full-load displacement, length, and width of aircraft carriers were selected. ARIMA(short-term within 5 years) and simple regression(long-term over 5 years) were used to estimate the future national competency of each country at the time of aircraft carriers acquisition. The relative efficiency score of the Korean-type aircraft carrier currently being evaluated is 1.062, and it was evaluated as small-scale aircraft carrier compared to the national competency. Based on Korean national competency, the optimal scale of the Korean-type aircraft carrier calculated by aggregating benchmark groups, is 58,308.1 tons of full-load displacement, 279.4m in length, and 68.3m in width.

본 연구의 목적은 색채 감성척도의 학술적, 실무적 활용 가치를 높이기 위해 색채 감성척도의 사용 현황과 개선 요인을 제시하는 것이다. 이를 위해 5년 이상 현업에 종사하고 있는 색채 전문가 25명을 대상으로 설문조사를 실시 하였다. 조사 구성 내용은 고바야시와 아이알아이 색채 감성척도에 대해 우선적으로 개선이 필요한 감성어휘를 도 출하고, 개선과 관련한 전문가들의 추가 의견을 수렴하였다. 분석 결과 1) 친숙도와 신뢰도에 대한 조사 결과는 아 이알아이가 더 높게 나타났다. 2) 필요성과 활용도 조사 결과 색채 감성척도가 필요하다는 응답이 88%로 나타났으 며, 연구, 교육 분야보다 기업 실무분야에서 필요하다는 의견이 43.6%로 가장 높게 조사되었다. 3) 개선 필요성 조 사 결과 아이알아이의 색채 감성척도의 개선이 필요하다는 의견이 88%로 나타났다. 4) 개선 필요 요인에 대해 가장 높은 응답은 시대성 반영이었으며, 고바야시 31.9%와 아이알아이 30.9%로 나타났다. 5) 색채 감성척도를 개선 할 경우 중요하게 또는 우선적으로 다루어질 필요가 있는 어휘는 모던한(15.8%) → 내추럴한, 낭만적인, 와일드한 (8.8%) → 다이내믹한(7.0%) → 고전적인, 캐주얼한, 시크한(5.3%) 순서로 조사되었다. 결과를 종합하면 실무 및 연 구 현장에서 색채 감성척도 사용에 한계를 인식하고 있었으며, 수정 보완에 대한 요구가 있음을 알 수 있었다.

In classical Chinese, the distinction between a rhetorical question and a simple question may not be readily clear when interrogative words are used. This paper aims to investigate factors that may determine whether a question formed with an安, yan焉, or heyi何以is a simple question or a rhetorical question; they include the presence of (1) a modal verb; (2) a negative marker in the main clause; (3) condition in the subordinate clause; and (4) a final exclamatory particle. Based on an analysis of these factors, a set of markers is proposed to distinguish a rhetorical question from a simple question and the extent of their reliability is discussed. Furthermore, a scale will be proposed to measure the strength of a rhetorical question based on the set of said markers.