해상특수교량은 특수한 환경적 조건뿐 아니라 고주탑의 구조형식, 보호재로 쌓여있는 케이블 등 특 수한 형식을 가지고 있어 일반적인 육안전검으로 안전점검을 할 수 없는 사각지대가 존재한다. 주탑의 외부 손상상태 및 케이블의 손상에 대해서는 정밀안전점검에서도 점검이 되지 않는 경우가 대부분이 므로 이에 대한 대책 마련이 시급하다. 또한 해상특수교량에 대한 전문적인 경험과 기술이 부족한 관 리자도 대상교량의 손상과 이상거동을 직관적으로 확인하고 판단할 수 있는 지원체계가 필요하다. 이 에 본 연구에서는 해상특수교량 고주탑에 대한 손상정보를 파악하기 위하여 드론의 자동비행 기술을 개발하고 이를 이용하여 주탑 외부 균열 손상에 대한 안전점검을 실시하고 이를 분석하였다.

PURPOSES : This study aimed to analyze the primary maintenance procedures and safety inspection checklist characteristics for suspension bridges. The study referred to the current suspension bridge safety management manual and conducted an on-site safety inspection. By comparing and analyzing any missing or inadequate inspection and management procedures, the study identified major inspection and management areas requiring improvement, and proposed potential solutions. METHODS : The study referred to the current suspension bridge safety management manual and conducted on-site safety inspections. By comparing and analyzing any missing or inadequate inspection and management procedures, the study identified major inspection and management areas requiring improvement, and proposed potential solutions. RESULTS : The study found that suspension bridges are currently inefficiently managed compared to other facilities subject to more rigorous maintenance and safety inspection. Therefore, maintenance and safety inspection procedures require improvement. CONCLUSIONS : For effective safety management and to reduce potential accident risk factors arising from negligent management, major improvements were suggested. Scientific maintenance and safety management could be achieved by incorporating enhancements into statutory requirements and improving management and inspection procedures. This long-term approach is likely to be more economical than the current methods, which lead to higher maintenance and repair costs and increased social costs from traffic accidents.

PURPOSES : This study aimed to secure the work space in alarm valve rooms to ensure stable working conditions for the engineers. METHODS : We analyzed situations where alarm valve room work spaces were inadequately secured posing a problem. Using the Ovako working posture analysis system (OWAS) method, we measured the body size of adult male technicians and their tools to analyze the actual space needed for them to maintain a healthy posture while working. On this basis, we proposed regulations governing workspace size and acceptable durations for unstable body postures. RESULTS : By measuring valve room work space and technician body size, we found that the workspace was inadequate for technicians. Applying OWAS showed that securing more space in the valve room improved the construction stability. CONCLUSIONS : Regulations on valve room size and appropriate work space for technicians will improve construction and inspection stability. This reduces the probability of poor construction and inadequate inspection, increasing the reliability of the firefighting facility system.

In this paper, we present a case study of developing MVIS (Machine Vision Inspection System) designed for exterior quality inspection of stamping dies used in the production of automotive exterior components in a small to medium-sized factory. While the primary processes within the factory, including machining, transportation, and loading, have been automated using PLCs, CNC machines, and robots, the final quality inspection process still relies on manual labor. We implement the MVIS with general- purpose industrial cameras and Python-based open-source libraries and frameworks for rapid and low-cost development. The MVIS can play a major role on improving throughput and lead time of stamping dies. Furthermore, the processed inspection images can be leveraged for future process monitoring and improvement by applying deep learning techniques.

The public safety management guidelines were introduced in 2019 and continue to be dedicated to advancing comprehensive measures for public safety management, with a primary focus on prioritizing the safety and well-being of the public within governmental institutions. To achieve this goal, our previous study developed a establishment procedure of risk assessment-based safety inspection system for public institutions that order construction projects and applied it to highway construction projects to evaluate its effectiveness. To enhance the practicality of the establishment procedure, it is essential to collect and analyze feedback from stakeholders regarding its performance and suitability. This study conducted a survey involving 200 participants who had experience with the establishment procedure, and performed statistical analyses to evaluate its performance and applicability. The survey results indicated that the participants reported a high level of satisfaction (scoring 4 and above on a 5-point Likert scale) in several areas: specialization of safety inspection items for different types of work (with a satisfaction rate of 65%), the evaluation process for safety ratings (64.5%), and their willingness to recommend the procedure to other institutions (75.5%). In the factor analysis with Varimax rotation, two factors emerged: (1) a specialization factor related to safety inspection items, and (2) a grading factor associated with safety evaluation results. Regression analyses of these factors unveiled significant positive relationships with improvements in safety and health performance, including the prevention of fatal accidents, heightened safety responsibility, and raised safety inspection standards. The establishment procedure of safety inspection system developed in our previous study can play a crucial role in reducing accidents resulting in fatalities and injuries at construction sites, ultimately contributing to a safer working environment for all involved parties.

The CTBTO is the Comprehensive Test Ban Treaty Organization to ban all forms of nuclear testing (underwater, air, and underground) worldwide and was adopted at the UN’s 50th annual general meeting in September 1996. As of September 2023, 187 out of 196 countries signed and 178 ratified. The Republic of Korea signed it in 1996 and ratified it in 1999. Several major Annex 2 countries still need to ratify it, and certain countries have not even signed it, so it has not come entry into force. The CTBTO has three verification systems for nuclear tests and consists of the International Monitoring System (IMS), the International Data Center (IDC), and On-Site Inspections (OSI). IMS consists of seismic, hydroacoustic, infrasound, and radionuclide monitoring. The measured data are delivered to IDC, analyzed by CTBTO headquarters, distributed raw data, and analyzed forms to member states. The final means of verification is in the field of OSI and will be operated when CTBT takes effect. Based on the IMS data, inspectors will be dispatched to the Inspected State Party (ISP) to check for nuclear tests. KINAC is attending the Working Group B, OSI technology development verification along with KINS and KIGAM. Since OSI is a means for final verification, integrated capabilities such as seismic and data interpretation and nuclides detection are required. CTBTO continues its efforts to foster integrated talent and modernize OSI equipment. Types of equipment include measurement, flight simulation equipment, and geographic information monitoring systems etcetera. KINAC is also developing equipment to detect contaminated areas using drones and probes. Development equipment is the nuclides detection and measurement of contaminated areas, and it is the equipment that prepares a control center and drops probes into suspected contamination areas to find a location of the radiation source. The probe can be used to track the location where the dose is most substantial through Bayesian estimation and source measurement.

Arms control treaties during the Cold War generally used national technical means (NTM) to verify treaty compliance. This was because signatory states refused to agree on on-site inspection (OSI) measures since it would require some level of intrusion. Efforts on nuclear arms control such as the Limited Test Ban Treaty (LTBT) or Strategic Arms Limitation Talks (SALT) initially included some form of OSI but could not continue due to refusal from signatory states. The Intermediate-Range Nuclear Force (INF) treaty concluded between the US and the Soviet Union in 1978 was significant since both states agreed on a highly intrusive verification measure. The Strategic Arms Reduction Treaty (START) and the new START also called for OSI measures similar to the INF. Alongside reducing a significant number of nuclear warheads and limiting specific types of nuclear warhead delivery vehicles, these treaties also provided basic models for conducting on-site inspection (OSI). OSI measures primarily rely on the political agreement between signatory states. However, the structure, types of inspections, number of inspections allowed, and technology/equipment used in each of the regimes also differ according to the objectives of each treaty. The INF treaty and START are salient cases as basic models for current nuclear disarmament verification research. Thus, this paper will conduct a case study on the procedures and mechanisms required for nuclear arms control verification in terms of OSI. Using the implications drawn from the INF treaty and START, this paper offers considerations for a potential nuclear disarmament verification.

The Agency needs to maintain a solid and reliable foundation for recruited inspectors by providing practical training at commercial nuclear power plants. The Comprehensive Inspection Exercise (CIE) is a basic training which consists of a simulation of a Design Information Verification (DIV) Visit, a Physical Inventory Verification (PIV) at a nuclear power plant, including Complementary Access. The basic curriculum includes a pre-course session, auditing exercises, fresh fuel (bundles and assemblies) measurements, spent fuel (bundles and assemblies) measurements, verification of design features, as well as nuclear material flow. ROK has been holding the lightwater reactor (LWR) / heavy-water reactor (CANDU) training course (CIE) from 2010 every year with about 2 weeks curriculum through MSSP (Member State Support Program). LWR and CANDU are operated by KHNP. To efficiently carry out the safeguards, IAEA receives the contribution through the ROK support program and implement R&D for the nuclear material inspection. ROK has been supporting and contributing total 22 tasks to IAEA in-cash and in-kind. Among them, this training provides for a course on safeguards verification activities at CANDU and LWR facilities. This course offers inspectors a unique opportunity to understand diversion scenarios and to familiarize themselves with instruments specifically used at CANDU and LWR facilities (OFPS and DCVD), as well as spent fuel dry storage transfer verification activities and dry storage dual sealing arrangements. KINAC performs PoC (Point of Contact) on behalf of NSSC and coordinates work between IAEA and KHNP. Additionally, KINAC first discusses with KHNP that can host light-water reactors and heavy-water reactors with KHNP at the beginning of each year. In order to hold a successful training, ROK plans and carries out a lot of process including agenda, accommodation, equipment movement, logistics and so on in consultation with the IAEA and facilities.

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.

Due to the aging of a building, 38.8% (about 2.82 million buildings) of the total buildings are old for more than 30 years after completion and are located in a blind spot for an inspection, except for buildings subject to regular legal inspection (about 3%). Such existing buildings require users to self-inspect themselves and make efforts to take preemptive risks. The scope of this study was defined as the general public's visual self-inspection of buildings and was limited to structural members that affect the structural stability of old buildings. This study categorized possible damage to reinforced concrete to check the structural safety of buildings and proposed a checklist to prevent the damage. A damage assessment methodology was presented during the inspection, and a self-inspection scenario was tested through a chatbot connection. It is believed that it can increase the accessibility and convenience of non-experts and induce equalized results when performing inspections, according to the chatbot guide.

Public institutions have a responsibility to ensure the safety of their employees and the public. One way to do this is to implement a systematic safety inspection system based on risk assessments and continuous improvements. This study developed a systematic safety inspection system for public institutions that are ordered construction projects. The proposed system in this study consists of a three-step process: (1) developing safety grade evaluation tables, (2) preparing and conducting safety inspections, and (3) evaluating and improving safety management grades. The first step is to develop safety grade evaluation tables by analysis and diagnosis of the construction site's work type, disaster statistics, and related laws. The second step is to conduct safety inspections using the developed evaluation tables. The third step is to determine the safety management grade based on the results of the safety inspection, and to improve risk factors found during the safety evaluation. The proposed system was implemented in highway construction projects carried out by public institutions. The results showed that the proposed system has two major effects: (1) reducing accident-related deaths and injuries, (2) improving safety management levels by continuous evaluation and improvement. The proposed system can be utilized in construction projects ordered by public institutions to improve the level of occupational safety and health.

근자에 헌법기관인 중앙선거관리위원회를 둘러싸고 2가지 쟁점이 문제가 되고 있다. 중앙선거관리위원회를 비롯한 선거관리위원회의 정치적 편향성 문 제 그리고 친인척 특혜채용과 관련한 내부 비위 문제에 대하여 감사원이 선 거관리위원회를 직무감찰할 수 있는지 여부가 바로 그것이다. 민주적 선거제도의 구현과 국민의 참정권의 완전한 실현을 위해서는 선 거관리를 담당하는 선거관리위원회의 정치적 중립성 유지가 무엇보다 중요 하다. 현행 헌법 시행 이후 비교적 정치적 중립성 유지를 잘 해왔던 선거 관리위원회가 2010년 이후 공고화된 양당 체제에 따른 정치적 대립의 격 화 등 다양한 요인으로 인하여 정치적 중립성을 유지하지 못하고 정부와 여당에 우호적인 편향성을 빈번하게 드러냈었는데 2017년 문재인 정부 출 범 이후 이러한 편향적 경향은 짙어져 여러 차례 정치문제로 비화되었다. 이러한 정치적 편향성 문제에 더하여 2023년에는 선거관리위원회 전·현직 공무원의 친인척 특혜채용 의혹이 불거져 사회적으로 큰 문제가 되었다. 그리하여 선거관리위원회의 친인척 특혜채용 의혹에 대하여 감사원이 직무 감찰에 나서야 한다는 여론이 강하게 제기되어 중앙선거관리위원회가 감사 원 직무감찰 대상기관에 해당되는지 여부가 법적 쟁점으로 부각되었다. 본 논문에서는 중앙선거관리위원회가 정치적 편향성을 드러내는 구조적 원 인이 중앙선거관리위원회 위원 9인 중 8인을 비상임으로 하고 대통령이 임명 하는 위원 중 1인을 상임위원으로 호선하는데 있음을 논증하였고 여기에 현직 대법관이 위원장으로 호선되어 중앙선거관리위원회 위원장을 겸직하는 오랜 관행도 중앙선거관리위원회 정치적 편향성에 간접적으로 원인제공을 한다는 점을 살펴보았다. 그리하여 중앙선거관리위원회 위원 전원을 상임직으로 전환 하는 동시에 대법원장이 대법관을 역임한 자를 중앙선거관리위원회 위원으로 지명하고 해당 피지명자를 위원장으로 호선하는 개선방안을 제시하였다. 한 편, 중앙선거관리위원회가 감사원의 직무감찰 대상기관에 해당하는지는 헌법의 문리적 해석, 역사적 배경, 선거관리위원회가 담당하는 사무의 법적 성격, 기능적 권력분립주의 등을 고려할 때 직무감찰 대상기관으로 볼 수 없음을 논 증하였으며 선거관리위원회의 내부적 비위나 직무태만 등에 대하여는 중앙선 거관리위원회의 내부적 감찰 활동에 우선 맡기고 내부적 통제가 미흡한 경우 국회나 수사기관 등에 의한 외부적 통제를 고려해야 함을 개선방안으로 제시 하였다.

목적 : 본 연구는 시선추적 분야에 사용되는 적외선 동공 검출 기법을 기반으로 동공 크기 변화와 동공 간 거리 변화 분석을 통해 양안시기능을 타각적으로 측정하는 방법에 관해서 연구하고자 한다. 방법 : 남녀 23명(평균연령 27.27±8.84세)을 대상으로 원거리(3 m) 및 근거리(0.4 m)에서 적외선 필터를 사 용하여 만든 차폐렌즈(이하 차폐렌즈)로 커버테스트를 실시하여 편위량을 측정하였다. 또한, 근거리에서 눈앞에 각각 ±1.00 D의 렌즈를 부가한 상태에서 커버테스트를 실시하여 AC/A 비 측정을 하였다. 적외선 카메라를 사용 하여 위의 과정들을 모두 촬영하였고, OpenCV(Open Source Computer Vision)를 사용하여 영상 프레임별 동 공 간 거리와 동공 면적을 계산하였다. 결과 : 원거리 및 근거리 커버테스트 측정값의 T-검정 결과 원거리 및 근거리 커버테스트 모두 통계적으로 유 의한 차이(p<0.050)가 없는 것으로 나타났고, Bland-Altman 일치도 평가에서도 대부분의 값이 두 측정법 사이 95% 신뢰구간 내에 존재하였다. 경사 AC/A 비는 -1.00 D를 가입했을 때 p=0.015, +1.00 D를 가입했을 때 p=0.823으로 –1.00 D 렌즈를 가입했을 때 유의미한 차이가 발생하였고, 계산 AC/A 비는 유의한 차이가 나타나 지 않았다. AC/A 비의 일치도 평가 역시 두 검사법 간 평균 차이가 0.9 △로 나타났고, 산점도 역시 평균 차이 선 에 균일하게 배열하여 비교적 높은 일치도를 보였다. 결론 : 본 연구에서는 시선추적 기술에 활용되는 적외선 동공 검출 기법을 기반으로 양안시기능의 타각적 검사 법을 개발하였다. 동공 크기 변화와 동공 간 거리 변화 양상 분석을 통한 타각적 양안시기능 검사 방법이 실제 임 상에 적용된다면, 자각적 검사 방법의 한계를 극복할 수 있을 것으로 생각된다.

Spent fuel from the Wolsong CANDU reactor has been stored in above-ground dry storage canisters. Wolsong concrete dry storage canisters (silos) are around 6 m high, 3 m in outside diameter, and have shielding comprised of around 1 m of concrete and 10 mm of steel liner. The storage configuration is such that a number of fuel bundles are placed inside a cylindrical steel container known as a Fuel Basket. The canisters hold up to 9 baskets each that are 304 L stainless steel, around 42” in diameter, 22” in height, and hold 60 fuel bundles each. The operating license for the dry storage canisters needs to be extended. It is desired to perform in-situ inspections of the fuel baskets to very their condition is suitable for retrieval (if necessary) and that the temperature within the fuel baskets is as predicted in the canister’s design basis. KHNP-CNL (Canadian Nuclear Lab.) has set-up the design requirements to perform the in-situ inspections in the dry storage canisters. This Design Requirements applies to the design of the dry storage canister inspection system.

A sample size calculation algorithm was developed in a prototype version to select inspection samples in domestic bulk handling facilities. This algorithm determines sample sizes of three verification methods satisfying target detection probability for defected items corresponding to one significant quantity (8 kg of plutonium, 75 kg of uranium 235). In addition, instead of using the approximation equation-based algorithm presented in IAEA report, the sample size calculation algorithm based on hypergeometric density function capable of calculating an accurate non-detection probability is adopted. The algorithm based the exact equation evaluates non-detection probability more accurately than the existing algorithm based on the approximation equation, but there is a disadvantage that computation time is considerably longer than the existing algorithm due to the large amount of computational process. It is required to determine sample size within a few hours using laptop-level performance because sample size is generally calculated with an inspector’s portable laptop during inspection activity. Therefore, it is necessary to improve the calculation speed of the algorithm based on the exact equation. In this study, algorithm optimization was conducted to improve computation time. In order to determine optimal sample size, the initial sample size is calculated first, and the next step is to perform an iterative process by changing the sample size to find optimal result. Most of the computation time occurs in sample size optimization process performing iterative computation. First, a non-detection probability calculation algorithm according to the sample sizes of three verification methods was improved in the iterative calculation process for optimizing sample size. A computation time for each step within the algorithm was reviewed in detail, and improvement approaches were derived and applied to some areas that have major effects. In addition, the number of iterative process to find the optimal sample size was greatly reduced by applying the algorithm based on the bisection method. This method finds optimal value using a large interval at the beginning step and reduces the interval size whenever the number of repetitions increases, so the number of iterative process is less than the existing algorithm using unit interval size. Finally, the sample sizes were calculated for 219 example cases presented by the IAEA report to compare computation time. The existing algorithm took about 15 hours, but the improved algorithm took only about 41 minutes using high performance workstation (about 22 times faster). It also took 87 minutes for calculating the cases using a regular laptop. The improved algorithm through this study is expected to be able to apply the sample size determination process, which was performed based on the approximate equation due to the complexity and speed issues of the past calculation process, based on the accurate equation.

A person who performs or plans to conduct a physical protection inspection as stipulated by the law, the act on physical protection and radiological emergency, should obtain an inspector’s ID card certified and authorized by Nuclear Safety and Security Commission Order No.137 (referred to as Order 137). In addition, according to Order 137, KINAC has been operating some training courses for those with the inspector’s ID card or intending to acquire it. Also, strenuous efforts have been put to incrementally elevate their inspection related expertise. Since Republic of Korea has to import uranium enriched less than 20% in order to manufacture fuels of nuclear reactors in domestic and abroad, the physical protection for categorization III nuclear material in transit is significantly important along with an increase in transport. The expertise of inspectors should be constantly needed to strengthen as the increase in transport leads to an increase in inspection of nuclear material in transit. We have suggested a special way to improve the inspector’s capacities through Virtual Reality technology (VR). A 3-Dimensional virtual space was designed and developed using a 3-axis simulator and VR equipment for practical training. HP’s Reverb G2 product, which was developed in collaboration with VALVE Corporation and MicroSoft, was used as VR equipment, and the 3-axis motion simulator was developed by M-line STUDIO corp. in Korea for the purpose of realizing virtual reality. The training scenarios of transport inspection consist of three parts: preparation at the shipping point, transport in route including stops and handover at the receiving point. At the departure point, scenario of the transport preparation is composed with the contents of checking the transport-related documents which should be carried by shipper and/or carrier during transport and confirming who the shipper and/or carrier is. Second, scenario is designed for inspector to experience how carrier and/or shipper protect the nuclear material during transport or stops for rests or contingency and how they communicate with each other during transport. Lastly, scenario is developed focusing on key check items during handover of responsibilities to the facility operator at the destination. Those training scenarios can be adopted to strengthen the capabilities of those with inspector’s ID card of physical protection in accordance with Order 137 and to help new inspectors acquire inspectionrelated expertise. In addition, they can be used for domestic education to promote understanding of nuclear security, or may be used for education for people overseas for the purpose of export of nuclear facilities.

Thin-film shape technology is recognized for its core technology to enhance the technology of LCD, PDP, semiconductor manufacturing processes, hard disks and optical disks, and is widely used to form coated thin films of products. In addition, resistance (electron beam filament) technology for heating is used to manufacture filament for ion implants used in semiconductor manufacturing processes. By establishing an electronic beam filament production system and developing seven specifications of electronic beam filament, it is contributing to improving trade dynamics and increasing exports to Japan through localized media of theoretical imports to domestic companies. In this study, CAE analysis was performed after setting electron beam filament specification and development objectives, facilities and fabrication for electron beam filament production, electron beam filament JIG & fixture design and fabrication followed by electron beam filament prototype. Then, the automation and complete inspection equipment of the previously developed electronic beam filament manufacturing facilities was developed and researched to mass-produce them, to analyze and modify prototypes, design and manufacture automation facilities, and finally, to design and manufacture the complete inspection equipment. In this paper, design and manufacture of electronic beam filament total inspection equipment for mass production were dealted with.

본 연구는 수직 벽체형 콘크리트 구조물의 정밀안전진단을 위한 외관조사시 고품질 정밀영상을 자동화된 방식으로 획득하여 균열손상을 탐지하고 시설물의 상태를 평가하기 위하여 개발된 등벽드론 탑재형 균열진단 시스템에 대한 것이다. 본 논문에서는 영상기반 균열진단 시스템을 이용한 정밀영상 획득기술, 자동화된 영상처리 알고리즘을 이용한 데이터 처리 기법을 제시하였으며, 실험적으로 도출된 지상표본거리를 기반으로 영상처리 자동화 알고리즘을 이용하여 생성된 균열모사 시험벽체의 평면전개 이미지 상 균열손상의 위치 정확도를 평가 분석하였다. 평가분석 결과, 가로축 길이 대비 최대 1.1%, 세로축 길이 대 비 최대 1.4%의 오차율을 보이는 것으로 나타났다. 제안된 영상 내 픽셀 좌표와 지상표본거리를 기반으로 균열손상의 위치를 추정하는 기법은 실측 좌표 대비 평균 1.0% 이하의 위치 오차를 가지는 것으로 평가되었다. 최종적으로 영상기반 진단과 긴급 보수와 같은 일반적인 시설물의 유지관리에 요구되는 위치 정확도를 확보하고 있는 것으로 분석되었다.