Guided missiles are a one-shot system that finishes their purpose after being used once, and due to the long-term storage until launch, the storage reliability is calculated during development, and performance is maintained through periodic inspections until the life cycle arrives. However, the reliability standards applied in the development of guided missiles were established by analyzing data accumulated by the United States during long-term operation in the country, and since they are different from our environment, the 00 guided missiles that have been deployed in the armed forces for more than 10 years under the premise that there is a difference from actual reliability. As a result of verifying the appropriateness of the current inspection cycle by analyzing the actual reliability of the missile, the necessity of changing the inspection period was derived because it was higher than the predicted reliability. It is proposed to build and utilize a lifespan management system that can systematically collect all data such as shooting and maintenance results by classification, and to establish a reliable reliability standard based on the accumulated data.

정부는 행정규제기본법 개정(‘19.07.17)을 통하여 경제활력 제고를 위하여 규제를 최소화하고 포괄적 네거티브 규제원칙을 적용하였다. 사전규제에서 우선허용-사후규제로의 정책환경이 변화하였다. 하지만 해양오염방제 자재․약제는 법적의무인증제도가 적 용되어 제품을 판매할 때마다 검정을 실시하여 제조업체의 자율성을 억제하여 왔다. 또한 방제자재․약제 생산업체는 대부분 영세하 여 구입자가 주문 의뢰 시마다 제품을 소량 생산하는 방식을 취하고 있다. 이에 해양오염방제 자재․약제 형식승인, 성능시험, 검정 제도도 시대의 흐름에 맞춰 시장 및 업계의 자율성을 보장하고 효율성 향상을 위해 규제완화의 필요성이 제기되었다. 본 연구에서는 현 제도의 문제점을 파악하고 국내․외 제도를 비교․분석을 통한 개선방안을 제안하였다.

Domestic ports are becoming increasingly complex due to the introduction of various marine 4th industry new technologies and the increase in marine logistics. Accordingly, the number of lightings behind the port is also increasing significantly, and there is a great demand for improving the visibility of the AtoN used as a means of transmitting information to vessel operators. This paper describes the development of the performance inspection system that can verify the synchronization and sequential flashing of maritime lanterns that is being introduced to enhance the visibility of AtoN.

We propose a method for developing an in-pipe inspection robot based on multiple inertial sensors. Estimating the position of underground pipelines where satellite signals do not reach remains challenging. High-precision inertial sensors and high-tech mobile robots can be solutions, but their high price limits their general use. We developed an in-pipe inspection robot by combining various low-cost sensors with a microcomputer-based RC car platform. First, we fabricated a multi-inertial sensors module by combining commercial grade low-cost MEMS inertial sensors. The sensor values measured by the multi-inertial sensor are transmitted to the main computer through the MCU, and the attitude angle of the vehicle is finally calculated through the inverse variance weighted average. The travel distance of the robot is estimated by using hall sensors and neodymium magnets attached to the inside of the wheels. Also, we measured the pipe diameter using multiple ultrasonic sensors. We verified the estimation accuracy of each sensor through experiments and consequently estimated the 3D trajectory of the in-pipe robot.

Recently, elevator inspection and self-examination were strengthened through the revision of the Elevator Safety Management Act, but there have been no significant reduction in serious accidents and major failures. Therefore, the government intends to lay the foundation for reflecting the safety quality rating system, which adjusts the elevator inspection cycle, as a policy to induce safety management of preemptive and active management entities. This study systematically reviewed and classified the safety quality rating system for elevator inspection cycle adjustment in previous studies, collected expert opinions, and reconstructed the key items into realistic evaluation items, and evaluated and scored the relative importance of each factor through the AHP technique.

The SLA 3d printer is the first of the commercial 3D printer. The 3D printed output is printed hanging on the bed that move to the upper position. Sandblasted bed is used to prevent layer shift. If sandblasting is wrong, the 3D printed output is layer shifted. For this reason, 3D printer manufacturing companies inspect the bed surface. However, the sandblasted surface has variety of irregular shapes and craters, so it is difficult to establish a quality control standard. To solve problems, this paper presents a standardized sandblasting histogram and threshold. We present a filter that can increase the classification rate.

Since 2015, the IAEA has been implementing inspections by changing the paradigm from a nuclear facility level perspective to state level approach in order to enhance effectiveness/efficiency, and random inspections have become a major means of paradigm conversion. From this point of view, Safeguards Division analyzed the implementation status of random inspection conducted in ROK over the past five years by type, facility, and year, and predict the future implementation direction. A total of 106 random inspections have been implemented in ROK over the past five years (2017- 2021). When classified by random inspection type, 20 Short Notice Random Inspections (SNRI), 9 Short Notice Inspections (SNI), 34 Unannounced Inspections (UI), and 43 Random Interim Inspections (RII) were performed, of which RII accounted for the largest proportion with about 40.6%. IAEA conducts customized random inspections according to the characteristics of each nuclear facility. In the past five years, 34 cases of LWR, 20 cases of Bulk Handling Facility, 22 cases of CANDU, 30 cases of random inspections were implemented at R&D facilities, with the largest proportion of LWR. In connection with this, as a result of analyzing the current status of random inspections by year, 19 cases in 2017, 21 cases in 2018, 20 cases in 2019, 19 cases in 2020, and 27 cases in 2021 were implemented, especially in 2021, an increase of about 40% compared to the previous year. In conclusion, the IAEA is increasing the proportion of random inspections every year in line with the updated SLA, and this stance is expected to be maintained in the future. This can be seen as proof that randomized tests are showing an increasing trend even in the COVID-19 pandemic situation that has occurred since December 2019. and, In the case of LWR, it is expected that the form of random inspection may vary depending on the direction of IAEA’s SLA improvement. Through these analyses, it is expected that the direction of future safeguards policy can be established.

The measurement activities to evaluate material balance of nuclear material are usually performed by operator. It is because that the IAEA does not have enough manpower to carry out nuclear measurement accountancy of all nuclear materials in the world. Therefore, the IAEA should consider scenarios which facility operator tries to divert nuclear material for misuse by distorting measurement record. It is required to verify the operator’s measurement data whether it is normal or not. IAEA measures inventory items using their own equipment which is independent of facility operator equipment for verification. Since all inventory lists cannot be verified due to limited resources, the number of items to be verified is determined through statistical method which is called as sample size calculation. They measure for the selected items using their own equipment and compares with operator’s record. The IAEA determines sample size by comprehensively considering targeted diverted nuclear material amount and targeted non-detection probability and performance of measurement equipment. In general, the targeted diverted nuclear material amount is considered significant quantity (plutonium: 8 kg, uranium-235: 75 kg). If the targeted non-detection probability or the performance of the verification equipment is low, the sample size increases, and on the contrary, in the case of high non-detection probability or good performance of verification equipment, even a small sample size is satisfied. It cannot be determined from a single sample size calculation because there are so many sample size combinations for each verification equipment and there are many diversion scenarios to be considered. So, IAEA estimates initial sample size based on statistical method to reduce calculation load. And then they calculate non-detection probability for a combination of initial sample size. Through the iteration calculation, the sample size that satisfies the closest to the target value is derived. The sample size calculation code has been developed to review IAEA’s calculation method. The main difference is that IAEA calculates sample size based on approximate equation, while in this study, sample size is calculated by exact equation. The benchmarking study was performed on reference materials. The data obtained by the code show similar results to the reference materials within an acceptable range. The calculation method developed in this study will be applied to support IAEA and domestic inspection activities in uranium fuel fabrication facility.

In this study is a study to measure the section by voltage through the high integration of the circuit of the inspection equipment for the power supply circuit of semiconductor equipment. The experiment was conducted by increasing the -1.5∼4 voltage section by 0.5V. At this time, the tolerance was applied to ±0.1%+5mA. Although the voltage increased through the experiment, the accuracy of the measurement data did not change, and it was confirmed through this experiment that the null hypothesis(H0) was adopted in each section through the hypothesis test.

해상에서 전복사고가 발생하면 선박이 복원성을 잃고 전복되는 과정에서 승선 하고 있던 선원의 사망․실종․부상 등 인명사고가 발생하는 동시에 전복에 따 른 선체 침수 및 침몰로 인해 선박 소유자는 엄청난 경제적 손실을 입게 된다. 따라서 동일한 전복사고가 발생하는 것을 방지하기 위해서는 현행 선박길이24미터 이상 어선에만 적용되는 복원성검사 및 만재흘수선 표시 규정에 대하 여, 허가받은 어업의 형태와 어구의 종류를 고려하여 총톤수 20톤 미만의 소형 어선으로 확대할 필요가 있다. 또한 기중기 등 조업에 사용하는 중량 어로설비 설치 유무에 따라 추가적인 복원성검사 및 만재흘수선을 표시하고, 사고선박에 대해서는 동일한 사고가 다시 발생하지 않도록 임시검사 규정을 강화하는 등 실질적이고 효과적인 검사 규정이 필요하다. 이에 따라 이 연구에서는 2017년부터 2021년까지 최근 5년간의 해양안전심판 원 재결서를 바탕으로, 자주 발생하고 있는 길이 24미터 미만의 소형어선 전복 사고 발생 원인과 소형어선 검사 규정의 문제점에 관한 연구를 통한 어선검사 규정 개선방안을 모색하였다.

Dry storage cask facilities are considered for temporary storage of spent nuclear fuels before their final disposal. According to relevant domestic laws and regulations, the integrity and gross defects of the PWR spent fuel must be inspected before they are transferred to the dry cask from a wet storage pool of a nuclear power plant. To meet nuclear safeguards requirements for a spent fuel transportation, the KINAC has been working to develop a simple and convenient Non-destructive Testing (NDT) equipment to verify the integrity and gross defects of the spent fuel assembly. This study was conducted in two processes. The first stage is to review the current NDT techniques conducted in the nuclear fuel manufacturing process. During the manufacturing process, the Ultrasonic testing (UT) and Eddy Current Testing (ECT) technique are used for detecting the cracks or foreign materials in a cladding of a fresh fuel. During an over-haul period after an end of one fuel cycle, the sipping test of the spent fuel is performed for detecting the failed fuel assemblies. If it is determined through the sipping test whether any fuel assembly contains a failed fuel rod, the failed fuel rod of lots of fuel rods in the assembly is found out using the UT instrument. The ECT is used for detecting the internal defects and oxide layer thickness of a fuel cladding. Because the UT and ECT are the wellknown technique and has already been employing for the spent fuel inspection, we adopted the UT and ECT technique for development of a new instrument for nuclear safeguards verification. The second stage is to design the UT and ECT equipment in consideration of nuclear safeguards activities in the spent fuel pool. For nuclear safeguards inspection, irradiated fuel or non-fuel items are distinguished. Thus, verification equipment newly designed using the UT and ECT should detect not only a failed rod, but also a false tube, or a false rod, or a different material from a cladding. New probe and signal processing methods are developed to achieve these goals. The design of UT and ECT probes are preferentially carried out according to technical requirements – the probe thickness including a damper material should be less than 1.0 mm - and the study on analyzing signal distortion caused from material difference will be conducted for development of the safeguards inspection equipment. Detailed results of our study will be discussed in this conference.

최근 10년간 국내에서 발생한 해양사고현황에 따르면, 총톤수 10톤 미만의 소형어선이 차지하는 비중은 전체 해양사고 중 47.51%로 높게 확인되었다. 또한 해양사고의 증가추세 역시 다른 선종/크기(총톤수)에 비해 매우 가파르게 증가하고 있어 이에 대한 대책마련이 시급한 실정이다. 한국해양교통안전공단에서는 소형어선의 선박검사제도 개선방안으로 자체검사제도의 도입을 제안한 바 있으며, 해양수산부에서는 최근 비대면 검사방법의 도입을 위해 ‘원격방식에 의한 선박검사 지침’을 마련하여 시행하였다. 본 연구에 서는 소형어선의 해양사고 감소 방안으로서 자체검사승인제도를 제시하고, 원격방식의 선박검사제도의 정형화 방안마련을 위해 모바 일 애플리케이션을 개발하여 실효성을 분석하였다. 그 결과 어선소유자의 자발적인 안전관리를 유도하기 위한 자체검사승인제도의 도 입과 함께 모바일 애플리케이션 기반 선박검사제도 도입의 필요성이 확인되었으며, 자체검사승인제도는 선박소유자의 안전의식을 고 취시켜 해양사고 감소에 대한 실효성이 있음을 확인하였다.

북한 핵에 대한 IAEA의 사찰이 2002년 종료된 이후 북한은 2017년에 여섯 번째의 핵실험과 ICBM급인 화성-15형을 시험 발사하고 핵무력을 완성하였다고 선언하였다. 그리고 북한은 2021년 초 조선노동당 8차 대 회에서는 핵고도화 선언을 하기도 하였으며 2022년 들어 극초음속미사 일, IRBM, ICMB 등을 시험발사하며 한반도 정세를 더욱 악화시키고 있 다. 시간이 경과할수록 북한의 핵능력은 더욱 확장되고 고도화할 가능성 이 많다. 한국과 미국을 포함하는 국제사회는 북한과의 비핵화 협상을 적극 추진하고 실질적 검증을 통해 북한의 완전한 비핵화를 달성해야 한다. 본 연구의 목적은 군비통제 검증 분야의 역사적 성공 사례인 INF 조약 이행과정 분석을 통하여 북한 핵에 대한 핵심적 검증과정인 현장사찰을 촉진하는 방안을 모색하는 것이다. 북한의 완전한 비핵화를 위한 협상에 서 가장 고비가 될 수 있는 검증의 현장사찰에 관한 실행가능하고 발전 적인 방안은 다음과 같다. 첫째, 북한을 NPT에 복귀시키고 IAEA의 안전 조치협정에 가입하도록 하여 ‘IAEA 주도의 현장사찰’을 실시하여야 한 다. 둘째, 북한 핵시설 중 미신고·미공개된 핵시설에 대한 ‘선택적이고 효과적인 현장사찰’이 이루어져야 한다. 셋째, 북한의 폐쇄적인 사회적 특수성을 고려하여 ‘상호협력적 현장사찰’이 이루어져야 한다. 넷째, 다 양한 국내 및 국제기술수단을 이용하여 원격 감시, 위성 및 항공 감시, 핵관련 인원의 인터뷰, 문헌조사, 시료 채취 및 정밀분석 등을 시행하는 ‘과학기술 집약적 통합 현장사찰’이 이루어져야 한다.