현재, 교통안전진단의 경우 차량 및 보행자의 교통사고를 미연에 방지하고 도로의 전체적인 안전을 도모하고자, 교통안전법 제34조 에 의거하여, 수행 조건에 부합한 경우 교통안전진단을 받도록 규정하고 있다. 교통안전진단의 경우 도로의 구분에 따라 다른 기준을 적용하고 있으며, 도로별 길이를 기준으로 수행 여부를 판단하고 있다. 교통안전진단의 경우 도로의 설계단계, 개시 전 단계 및 운영단계 등 3가지로 구분되어 수행되고 있으며, 각각의 단계별로 진단 수행 내용 및 범위가 조금씩 다르게 진행된다. 설계 단계에서의 교통안전진단의 경우, 해당 도로의 실시 설계 내용을 바탕으로 도로의 안전 을 판단하며, 개시 전 단계의 경우 도로의 신설 이후 운영 전 도로의 안전을 평가한다. 마지막으로 운영 단계의 교통안전진단의 경우 현재 운영 중인 도로에 대하여 도로의 안전을 평가하는 것이다. 본 연구에서는 진단단계별 교통안전진단 중 도로 설계단게에서 수행 시 발생될 수 있는 한계점을 파악하고, 이를 보완할 수 있는 방 안을 제시하여 그 효과를 분석하고자 한다. 또한, 국제 기준으로 운영되고 있는 iRAP(International Road Assessment Programme)의 SR4D( Star Rating for Design)을 통해 설계단계의 교통안전진단 수행 시 효과적이고 안전한 진단결과를 도출해내고자 한다.

Because most spent nuclear fuel storage casks have been designed for low burnup fuel, a safety-significant high burnup dry storage cask must be developed for nuclear facilities in Korea to store the increasing high burnup and damaged fuels. More than 20% of fuels generated by PWRs comprise high burnup fuels. This study conducted a structural safety evaluation of the preliminary designs for a high burnup storage cask with 21 spent nuclear fuels and evaluated feasible loading conditions under normal, off-normal, and accident conditions. Two types of metal and concrete storage casks were used in the evaluation. Structural integrity was assessed by comparing load combinations and stress intensity limits under each condition. Evaluation results showed that the storage cask had secured structural integrity as it satisfied the stress intensity limit under normal, off-normal, and accident conditions. These results can be used as baseline data for the detailed design of high burnup storage casks.

The aim of this study is to ensure the structural integrity of a canister to be used in a dry storage system currently being developed in Korea. Based on burnup and cooling periods, the canister is designed with 24 bundles of spent nuclear fuel stored inside it. It is a cylindrical structure with a height of 4,890 mm, an internal diameter of 1,708 mm, and an inner length of 4,590 mm. The canister lid is fixed with multiple seals and welds to maintain its confinement boundary to prevent the leakage of radioactive waste. The canister is evaluated under different loads that may be generated under normal, off-normal, and accident conditions, and combinations of these loads are compared against the allowable stress thresholds to assess its structural integrity in accordance with NUREG-2215. The evaluation result shows that the stress intensities applied on the canister under normal, off-normal, and accident conditions are below the allowable stress thresholds, thus confirming its structural integrity.

A transfer cask serves as the container for transporting and handling canisters loaded with spent nuclear fuels from light water reactors. This study focuses on a cylindrical transfer cask, standing at 5,300 mm with an external diameter of 2,170 mm, featuring impact limiters on the top and bottom sides. The base of the cask body has an openable/closable lid for loading canisters with storage modules. The transfer cask houses a canister containing spent nuclear fuels from lightweight reactors, serving as the confinement boundary while the cask itself lacks the confinement structure. The objective of this study was to conduct a structural analysis evaluation of the transfer cask, currently under development in Korea, ensuring its safety. This evaluation encompasses analyses of loads under normal, off-normal, and accident conditions, adhering to NUREG-2215. Structural integrity was assessed by comparing combined results for each load against stress limits. The results confirm that the transfer cask meets stress limits across normal, off-normal, and accident conditions, establishing its structural safety.

Spent nuclear fuel management is a high-priority issue in South Korea, and addressing it is crucial for the country’s long-term energy sustainability. The KORAD (Korea Radioactive Waste Agency) is leading a comprehensive, long-term project to develop a safe and effective deep geological repository for spent nuclear fuel disposal. Within this framework, we have three primary objectives in this work. First, we conducted statistical analysis to assess the inventory of spent nuclear fuel in South Korea as of 2021. We also projected future generation rates of spent nuclear fuels to identify what we refer to as reference spent nuclear fuels. These reference spent nuclear fuels will be used as the design basis spent fuels for evaluating the safety of the repository. Specifically, we identified four types of design basis reference spent nuclear fuels: high and low burnup from PLUS7 (with a 16×16 array) and ACE7 (with a 17×17 array) assemblies. Second, we analyzed radioactive nuclides’ inventory, activities, and decay heats, extending up to a million years after reactor discharge for these reference spent nuclear fuels. This analysis was performed using SCALE/TRITON to generate the burnup libraries and SCALE/ORIGEN for source term evaluation. Third, to assess the safety resulted from potential radioactive nuclides’ release from the disposal canister in future work, we selected safety-related radionuclides based on the ALI (Annual Limit of Intake) specified in Annex 3 of the 2019-10 notification by the NSSC (Nuclear Safety and Security Commission). Conservative assumptions were made regarding annual water intake by humans, canister design lifetime, and aquifer flow rates. A safety margin of 10-3 of the ALI was applied. We selected 56 radionuclides that exceed the intake limits and have half-lives longer than one year as the safety-related radionuclides. However, it is crucial to note that our selection criteria focused on ALI and half-lives. It did not include other essential factors such as solubility limits, distribution coefficients, and leakage processes. So, some of these nuclides can be removed in a specific analysis area depending on their properties.

Construction industry is considered as one of the most high-risk industries for work-related injuries and fatalities, accounting for more than half of fatalities in Korea. Advanced countries have recognized the critical role of designers in preventing construction accidents and have established regulations on design for safety. In line with this, the Korean government have also implemented regulations that require owners and designers to review the safety of design outcomes. However, it has been observed that designers face challenges in identifying hazards and integrating design solutions at the design stage mainly due to their shortage of required knowledge and skills. This study aimed to examine design solutions that can be applied to prevent fall accidents in the construction industry, and to establish a relationship between these solutions and fatal fall accidents occurred over the past three years in Korea. This study also analyzed the relationships of four variables (construction type, cost, work type, and fall location) with design solutions. The results indicated that all four variables have significant relationships with design solutions, with fall location showing the strongest relationship. The design solutions and their relationships with fatal fall accidents identified in this study can be utilized in identifying hazard and integrating design solutions to ensure design for safety.

자율주행 5단계(mind-off)에서는 운전에서 해방된 탑승자가 차량 내에서 대면 대화, 업무, 휴식, 영화 감상 등의 다양한 활동이 될 것으로 예상된다. 특히 자동차 실내 공간의 다양한 변화가 예상된다. 또한 미국자동차협회(American Automobile Association)가 시행한 조사에서 73%가 자율주행 자동차에 탑승하는 것이 두렵다고 응답하였고, 자율주행 5단계에서는 안전의 주체가 자율주행자동차로 이양이 예상되므로 사용자 경험 관점에서 연구가 이루어져야 한다. 최근 완전자율주행자동차의 안전성 확보에 관한 다양한 연구가 이뤄지고 있으나 실제 탑승자의 심리적 안전성 확보 관점에서의 연구는 부족한 실정이다. 이에 본 연구는 AHP 분석 기법에 기반하여 설문조사를 진행하였다. 그 결과 각 실내 행위 유형에 따라 탑승자의 심리적 안전성 확보를 위한 자동차 안전장치의 우선순위를 도출하였고 도출된 결과를 기반으로 탑승자의 심리적 안전성을 확보를 위한 실내 공간을 제시하였다. 본 연구는 탑승자의 심리적 안전성을 충족하는 실내공간 설계를 위한 방향성을 제시한 것에 의의가 있으며, 이를 바탕으로 사용자의 심리적 안전성 확보를 위한 완전 자율주행 자동차 실내 환경 조성이 이루어질 것으로 기대한다.

대형선박의 발전에 사용되는 증기터빈에는 핵심부품으로서 노즐플레이트가 활용되는데 정밀 산업 이 발전한 요즘에도 오래 전의 설계와 생산방식을 답습하고 있다. 노즐플레이트는 많은 터빈 블레이드와 이너링, 아우터링으로 구성되어 있고 이들을 서로 용접하여 제작한다. 용접 시에 블레이드의 뒤틀림 등으로 인하여 그 용접위치에 약간의 변위가 발생하여 각 블레이드 간의 pitch가 불균일하여지고 이로 인해 플레이트의 성능 저하가 우려된다. 이러한 점을 개선하기 위해 용접식 보다는 pitch의 등간격을 유지시키는데 유리한 조립식 설계로 전환하는 것이 필요하다. 이는 설계 변경을 해야 하며 또한 새로운 설계 시에 그에 대한 응력을 기초로 하는 구조해석과 장시간 사용되었을 경우에 대비하여 내구성 시험이 수반되어야 한다. 본 연구는 터빈 블레이드의 구조 설계를 조립식으로 변경하고 이의 결합성을 검토한 후 사이버 공간상에서 안전성 검증을 통하여 실용 가능성을 입증하고자 한다.

With the development of industrial technology and science, production and manufacturing facilities have been enhanced and improved, and the importance of the safety of workers has also been regulated and limited by various safety management methods. As a way to secure the safety of the workers from the production facility, the fail-safe and fool-proof methods are now being applied. Any possible insecure behavior and unsafe conditions can be removed by adopting the standards and specifications that are now secure the safety of workers and equipment. This research analyzes EN ISO 13849-1 international and European standards during CE certification. In order to secure acceptable reduced risks, the risk assessment process of ISO 12100 and the processes for reducing its risk are applied. In the current ISO 13849-1 standard, the criteria for the required performance level PLr (Required Performance Level) for the applicable risk and safety functions through the risk assessment are subjective and not subdivided. Therefore, the evaluation criteria are likely to cause judge’s judgement error due to qualitative judgement. This research focuses on evaluation and acceptable performance level setting for the safety circuit of the equipment. We propose an objective and specific evaluation criteria to secure safety, and the proposed evaluation criteria are applied to the case study of the safety circuit for the equipment. In order to secure the safety of the entire safety circuit, the improvement of the MTTFd and DC level related to the SRP/CS (Safety-Related Parts of Control Systems)’ lifetime is required for the future research.

This thesis provides background information on DFS carried out by the government in an effort to reduce the accident rate, cases of DFS in other advanced countries to study their risk detection, risk assessment, risk control measures, and cases in which application of DFS during the designing phase succesfully led to reduction of the accident rate. Till now, the focus has been on incident responses after the occurance of accidents, it describes the importance of considering safety during the desining process through safety results and cases.

Safety flight training can be done, through the platform proposed in this paper. This paper designed a flight dynamic model and identified essential functions in order to enable pilots to simulate a training environment similar to the actual. It also design activity diagram, concept as well as class diagram. This paper presents the main features and direction of aircraft to be equipped in the future standard platforms. By design main class of flight dynamic and description. it will help developer to setup the standard platform for aircraft simulation.