본 연구는 도로 프로젝트의 설계 단계에서 ESG(환경, 사회, 지배구조) 요소를 효과적으로 적용할 수 있는 구체적인 지표를 개발하고 제안하는 것을 목적으로 한다. 최근 글로벌 경영 환경에서 ESG의 중요성이 증대됨에 따라, 대규모 인프라 사업인 도로 프로젝트에서도 ESG 요소의 체계적인 적용이 요구되고 있다. 본 연구에서는 GRI, SASB, CDP 등 국제적 ESG 표준을 분 석하고, 도로 프로젝트의 설계 단계를 세부적으로 검토하여 각 단계에 적합한 ESG 지표를 개발하였다. 연구 결과, 프로젝트 목표 설정부터 지속가능성 고려까지 각 설계 단계별로 적용 가능한 구체적인 ESG 지표를 제시하였다. 이는 에너지 효율, 온 실가스 감축, 생태계 보호, 지역사회 참여, 자원 효율성, 안전 기준 등을 포함한다. 본 연구에서 제안된 지표는 도로 프로젝트 의 환경적 영향을 최소화하고, 사회적 가치를 증진하며, 투명하고 책임 있는 프로젝트 운영을 가능케 하는 실질적인 가이드라 인을 제공한다. 이를 통해 도로 프로젝트의 지속가능성을 제고하고 사회적 가치 창출에 기여할 수 있을 것으로 기대된다.

외국인 유학생이 꾸준히 증가함에 따라 정부는 ‘외국인 유학생 유치‧관 리 역량 인증제’를 시행하였다. 인증제는 외국인 유학생 유치 및 관리에 양적인 성장뿐만 아니라 질적인 성장에 목적을 두고 2012년 본격적으로 도입하였으며 현재는 ‘교육국제화역량 인증제’로 확대하여 실시되고 있 다. 이를 통해 교육의 질과 학생의 수준을 끌어올리고 있지만 인증제가 현실을 반영하지 못하는 부분이 있다. 이에 본고에서는 외국의 사례를 조사한 후 한국의 교육국제화역량 인증제가 어떻게 수정·보완되어 왔는 지 그동안의 변화 과정을 살펴보고 3주기 보완 체계가 진행 중인 현재의 평가 항목과 기준 내용의 보완점을 제언하였다. 제언의 내용은 크게 세 가지로 나누어 볼 수 있다. 먼저 불법체류율 산정 방식이다. 기존의 산정 방식은 모수와 분자의 조건을 동일하게 보았기 때문에 이를 악용하는 경 우도 있었다. 따라서 불법체류율 산정 방식을 수정해야 한다. 둘째, 학위 과정의 경우 공인 한국어능력 자격을 취득하지 않은 유학생 대상 한국어 강의에 대한 명확한 규정이 필요하며 구체적인 졸업 요건이 명시되어야 한다. 셋째, 어학연수과정의 학생수, 교원 자격증 수 등을 현장 상황을 파악하여 평가 기준을 높여야 한다.

본 연구에서는 국내 아스팔트 도로 현장에서 발생한 동절기 도로융기 현상의 발생 원인을 현장 규명하고 동결융해 피해를 보수하고 자 현장조사, 현장 LFWD실험 및 포장 코어채취, 지하수위 측정, 기상데이터 및 설계자료 분석 등을 실시하였다. 본 연구의 동상 원인 분석은 추후 동결융해 피해 재발방지를 위한 적정한 보수보강공법을 선정하기 위해 수행하였다. 분석과정은 지하수위 상승에 의한 동 상피해 가능성, 동결깊이 과소설계에 의한 동결융해 가능성, 포장면 표면수 유입에 의한 동결융해 가능성, 도로 외측 비포장면을 통한 수분유입과 이에 의한 동결융해 가능성으로 조사하여 동상 원인을 파악하였다. 또한 현장에서 소형충격 재하시험 LFWD(Falling Weight Deflctometer)시험을 하여 포장의 구조적 지지력을 측정하여 얻은 처짐값을 통해 포장체 구조적 능력을 분석함과 동시에 도로융기와의 연관성을 파악하여 균열분석 결과를 함께 분석하고 보수방법을 제안하였다.

A provision crane is installed on the stern deck of the ship to load or unload ship supplies. In this study, a ventilation hole capable of circulating internal flow was installed to reduce dew condensation by reducing the temperature difference between the inside and outside of the cylindrical column supporting the provision crane installed at the stern of the training ship. In order to reduce the temperature difference between the inside and the outside, an anti-sweat covering work was carried out by adding insulation material. By reducing dew condensation, we aim to improve the insulation of the electric motor installed inside the cylindrical column and improve the usability of the provision crane

The ductility of the system based on the capacity of each structural member constituting the seismic force-resisting system is a significant factor determining the structure’s seismic performance. This study aims to provide a procedure to supplement the current seismic design criteria to secure the system’s ductility and improve the seismic performance of the steel ordinary moment frames. For the study, a nonlinear analysis was performed on the 9- and 15-story model buildings, and the formation of collapse mechanisms and damage distribution for dynamic loads were analyzed. As a result of analyzing the nonlinear response and damage distribution of the steel ordinary moment frame, local collapse due to the concentration of structural damage was observed in the case where the influence of the higher mode was dominant. In this study, a procedure to improve the seismic performance and avoid inferior dynamic response was proposed by limiting the strength ratio of the column. The proposed procedure effectively improved the seismic performance of steel ordinary moment frames by reducing the probability of local collapse.

디지털 기술은 단순한 정보 전달 수단을 넘어서, 서사를 생성하고 소비하는 방식을 재정의하는 새로운 형태 의 패러다임이다. 디지털 기술의 발전과 함께, 디지털 매체는 강력한 스토리텔링 도구로서 현대 교육 분야에 자리 잡고 있으며, 이는 전통적인 교육 방식과 비교했을 때 학습자의 상호작용이 강조된다는 차이가 있다. 본 연구는 이러한 디지털 스토리텔링 환경에서 시·청각이 결합된 정보를 학습자에게 제공하고, 스토리텔링 과정에 선택지를 제공함으로써 상호작용성과 게임 요소를 더해 학습자 스스로 스토리텔링을 통해 학습하는 방법을 제안하였다. 그리고 연구의 타당성 검증을 위해 전문가 인터뷰를 실시하였다. 전문가 검증결과, 학습 자 스스로 스토리텔링을 통해 학습하는 과정은 이해도와 몰입도 측면에서 매우 효과적일 것이라는 긍정적인 답변을 얻을 수 있었다.

Particulate matter is known to have adverse effects on health, making it crucial to accurately gauge its concentration levels. While the recent advent of low-cost air sensors has enabled real-time measurement of particulate matter, discrepancies in concentrations can arise depending on the sensor used, the measuring environment, and the manufacturer. In light of this, we aimed to propose a method to calibrate measurements between low-cost air sensor devices. In our study, we introduced decision tree techniques, commonly used in machine learning for classification and regression problems, to categorize particulate matter concentration intervals. For each interval, both univariate and multivariate multiple linear regression analyses were conducted to derive calibration equations. The concentrations of PM10 and PM2.5 measured indoors and outdoors with two types of LCS equipment and the GRIMM 11-A device were compared and analyzed, confirming the necessity for distinguishing between indoor and outdoor spaces and categorizing concentration intervals. Furthermore, the decision tree calibration method showed greater accuracy than traditional methods. On the other hand, during univariate regression analysis, the proportion exceeding a PM2.5/PM10 ratio of 1 was significantly high. However, using multivariate regression analysis, the exceedance rate decreased to 79.1% for IAQ-C7 and 89.3% for PMM-130, demonstrating that calibration through multivariate regression analysis considering both PM10 and PM2.5 is more effective. The results of this study are expected to contribute to the accurate calibration of particulate matter measurements and have showcased the potential for scientifically and rationally calibrating data using machine learning.

When aluminum is in an alkaline state, the aluminum oxide film surrounding aluminum is dissolved and moisture penetrates the exposed aluminum surface, causing corrosion of aluminum. At this time, hydrogen gas is generated and there is a risk of explosion due to the generated hydrogen gas. Aluminum radioactive waste is difficult to permanently dispose of because it does not meet the standards for the acquisition of low- and intermediate-level radioactive waste cave disposal facilities currently managed and operated by the Korea Nuclear Environment Corporation. However, because of this risk, it is necessary to study how to safely treat and dispose aluminum waste. In this study, overseas cases were investigated and analyzed to ensure the safety of aluminum waste disposal, and the current status of aluminum radioactive waste generated during decommissioning of the Korea Research Reactor 1&2 and a treatment plan to secure disposal suitability were presented. The process of removing a little remaining oxygen in molten steel during the reduction of iron oxide in the iron refining process is called deoxidation, and a representative material used for deoxidation is aluminum. In the case of metal melting decontamination, which is one of the decontamination processes of radioactive metal waste, a method of treating aluminum waste by using aluminum as a deoxidizer is proposed.

Concentrated effluent and spent ion exchange resins (IERs) from nuclear power plants (NPPs) were generated prior to the establishment of a disposal facility site and waste acceptance criteria have been temporarily stored at the NPPs because their suitability for disposal has not been confirmed. In particular, at the Kori Unit 1, which was the first to start the commercial operation in South Korea, the initially generated concentrated effluent and IERs are repackaged in large size of concrete containers and stored without provided regulation standard. The concentrated effluent is package as cementitious form in 200 L drums and repackaged in concrete containers, case of the IERs were solidified or dehydrated and repackaged in round concrete container. In this study, we review and propose a disposal plan for concentrated effluent and IERs repackaging drums that have not been confirmed to be suitable for disposal from the first operating nuclear power plant, Kori Unit 1, 2. First, the concentrated effluent was stored in four 200 L drums respectively, and then, it was again stored in concrete container and which was poured on top using grouted concrete. Therefore, the process was required by cutting concrete container for extracting the internal drums at first. Internal radioactive waste should be crushed to the suitable waste criteria and solidified, finally disposal in to the polymer concrete high integrity container (PC-HIC). IER was repackaged and disposal in square type of 200 L concrete drums respectively covered the cap. So, extracting the internal drums should be extracted after removing the cap of external concrete container. Cement solidification drums can be crushed and re-solidified or disposed in the PC-HIC. Stored IER after dehydrated can be disposal in PC-HIC. In conclusion, the container was used as a package that repackaging the concentrated effluent and IER was separated into two different types of waste depending on the level of contamination of radioactivity, the polluted area is disposed of as radioactivity contamination or the unspoiled area will be treated as self-disposal waste.

Ring Tensile Test (RTT) is mainly performed for comparing tensile strength and total strain between nuclear fuel cladding specimens under various initial conditions. Through RTT, the loaddisplacement (F-D) curve obtained from the uniaxial tensile test can also be obtained. However, the Young’s modulus estimated from the gradient of the straight portion is much lower than general value of materials. The reasons include tensile machine compliance, slack in the fixtures, or elastic deformation of the fixtures and the tooling. Another reason is that the bending of the test part in the ring is stretched with two pieces of tools. Although the absolute value of the Young’s modulus is smaller than the actual value, it is applicable to calculate the ratio of the Young’s moduli of different materials, that is, the relative value. The Young’s modulus, or slope of the linear section, varies slightly depending on which location data is used and how much data is included. In order to obtain a more accurate ratio of Young’s moduli between materials using the RTT results, a post-processing method for the ring tensile test results that can prevent such human errors is proposed as follows. First, the slope of the linear section is obtained using the displacement and load when the load increase is the largest and the displacement and load of the position that is 95% of the maximum load increase. To replace the section where the ring-shaped specimen is stretched at the beginning of the F-D curve, a straight line equal to the slope of the linear section is drawn to the displacement axis from the position of maximum load increase and moved to the origin to obtain the final F-D curve for a RTT. Lastly, the yield stress uses the stress at the point where the 0.2% offset straight line and the F-D curve meet as suggested in the ASTM E8/E8M-11 “Standard test methods for tensile testing of metallic materials”. RTT results post-processing method was coded using FORTRAN language so that it could be performed automatically. In addition, sensitivity analysis of the included data range on the Young’s modulus was performed by using the included data range as 90%, 85%, and 80% of the maximum load increase.

Among the public notices of the NSSC, five notices related to safeguards, including “Education of Nuclear Control, International Regulatory Materials, Preparation of Regulation of NMAC (Nuclear Material Accounting and Control), the National Inspection of NMAC, and Reporting of International Regulatory Materials” The regulations on the National Inspection of NMAC have remained the same since some revisions were made on December 26, 2017, raising the need to revise the public notice due to changes in the domestic and international safeguards regulatory environment. Accordingly, this paper analyzes the public notice of the National Inspection of NMAC and proposes the revision direction. The regulation regarding the National Inspection of NMAC comprises sections such as Purpose and Definition, Types - Scope - Frequency of the National Inspection, Notification of the National Inspection’s plan, and Management of Violation. Appendices include the contents of the violation table, explanations regarding types of violations, and various forms related to the National Inspection, which are attached separately. IAEA mentioned that ROK was selected as a pilot country for the Improved SLA (State-Level Approach) project starting in November 2020. IAEA explained that a quantitative and standardized methodology was adopted and developed for this purpose. As a result, the Unannounced Inspection at LWR facilities will transition to the Random Interim Inspection. Additionally, the Physical Inventory Verification in CANDU facilities will increase to once a year per reactor. This status will change the frequency and intensity of inspection at domestic nuclear facilities. Furthermore, domestically, there is an ongoing trend of continuous growth and diversification of nuclear facilities. In light of the changing domestic and international safeguards environment, it is necessary to set a direction for revising the regulation regarding the National Inspection of NMAC that was partially amended in 2017 to align with the current status. Firstly, due to the increased burden on operators resulting from the increased number of IAEA inspections following the application of Improved SLA, there is a need to streamline the National Inspection of NMAC frequency to enhance overall regulatory efficiency. Furthermore, the definition section should also be revised to include matters related to the regulation to reflect the current reality accurately. Considering the operation and name changes of new domestic nuclear facilities, there may be a need to add or modify computer input codes. While pursuing the revision of regulations regarding the National Inspection of NMAC, an analysis of the need for revision of other regulations related to safeguards should also be conducted, and directions should be set. Through this process, improving the regulatory framework that forms the basis of safeguards can help prevent confusion among operators and promote regulatory efficiency. We can better cope with these changes by proactively adapting to the rapidly changing domestic and international nuclear environment.

본 연구는 해양산업시설에서 배출되는 위험·유해물질(Hazardous and Noxious Substances) 중 아연을 대상으로 국내 서식종을 기반 으로 한 독성시험을 수행하고, 그 결과를 활용하여 국내 실정에 맞는 아연의 해양 수질 준거치(Marine Water Quality Criteria)를 제안하였다. 시험생물은 국내 연근해에 분포하고 산업적으로 유용하며, 표준 시험방법이 존재하는 종을 우선으로 5개의 분류군(Algae, Rotifer, Crustacean, Mollusc, Fish)의 총 10종을 선정하여 독성시험을 수행하였으며, 급·만성비(Acute-Chronic Ratio) 산출을 위하여 무척추동물, 어류 분류군에 대한 만성독성시험을 수행하였다. 국내종 독성시험에서 산출된 독성값을 활용한 수질준거치는 US EPA의 CCC (Criterion Continuous Concentration) 산출 기준으로 9.56 ㎍/L, 호주/뉴질랜드의 산출 기준으로 15.50 ㎍/L 로 나타나 호주/뉴질랜드에서 권고하는 기준인 14.40 ㎍/L 와 유사하였다. US EPA 및 호주/뉴질랜드는 자국의 생태독성 데이터베이스(US EPA Ecotox Database, Australasian Ecotoxicology Database)를 보유하고, 신뢰도 높은 독성값들을 생성하여 수질 기준 및 산출 기준을 갱신하고 있다. 한편, 국내에서는 국내종 기반 급성 독 성값을 적용하고 있지만, 중요한 산출 지표인 급·만성비는 US EPA 또는 유럽의 결과값을 활용하여 해양 수질 준거치를 산출하고 있으며, 국내의 생태독성 자료 또한 제한적인 실정이다. 따라서, 국내 해양 서식종을 기반으로 한 지속적인 독성시험과 준거치 설정 체계를 확보하 여 국내 해양생물과 생태계를 보호할 수 있는 해양 수질 준거치 도출이 필요할 것으로 판단된다.

United States Nuclear Regulatory Commission (U.S. NRC) specifies regulations on obtaining licenses and describes the technical position on the average waste concentration, also known as Concentration Averaging and Encapsulation Branch Technical Position (CA BTP); CA BTP helps classify blendable waste and discrete items and address concentration averaging. The technical position details are reviewed and compared in a real environment in Korea. A few cases of concentration averaging based on the application of CA BTP to domestic radioactive waste are presented, and the feasibility of the application is assessed. The radioactive waste considered herein does not satisfy the Disposal Concentration Limit (DCL) of the second-phase disposal facility while applying the preliminary classification. However, if CA BTP is applied when the radioactive waste is mixed with other radioactive waste items in a large and heavy container, it can be disposed of at the second-phase disposal facility in Gyeongju Repository. To apply the CA BTP of the U.S. NRC, it is necessary to investigate the safety assessment conditions of the US and Korea.

KDS 41 12 00의 풍하중 관련 식은 정형적인 건축물에 대한 수많은 연구를 통해 만든 경험식이다. 따라서 비정형 건축물에 대하여 KDS 41 12 00에 따라 풍하중을 산출하면 건축물의 형상이 반영되지 않아 실제 풍하중과 상이할 수 있다. 이에 Y자형 건축물 에 대하여 풍동실험에 따른 풍하중과 KDS 41 12 00에 따른 풍하중을 산출하고 비교하고자 하였다. 이를 위해 풍력실험을 수행하였고 최종적으로 두 가지 방법에 따른 풍하중의 비율을 산출하고 이를 풍하중 증감계수로 도출하고자 하였다. 본 연구에서 제시하는 풍하 중 증감계수를 KDS 41 12 00에 따라 풍하중 산출 과정에 적용한다면 보다 합리적으로 Y자형 건축물에 대한 풍하중을 산출할 수 있 을 것으로 사료된다.