PURPOSES : Recently, interest in radioactive accidents has increased due to domestic and international nuclear power plant accidents. In particular, local residents' concerns are increasing due to safety issues such as radioactive leaks at the Hanbit Nuclear Power Plant in South Korea. As Gwangju Metropolitan City is not included in the emergency planning area set by the Nuclear Safety and Security Commission, there are significant limitations to establishing disaster prevention measures for nuclear power plant accidents. Considering the Fukushima and Hanbit nuclear power plant accidents, the improvement of Gwangju Metropolitan City's radioactive leak accident response manual is urgently required. This study aimed to establish disaster prevention measures to respond to nuclear power plant accidents in Gwangju Metropolitan City in the event of a Hanbit Nuclear Power Plant accident and to improve resident protection measures by estimating the arrival time of radioactive materials and radiation dosage through a nuclear power plant accident simulation. Additionally, we aimed to supplement the on-site action manual for radioactive leaks at the Hanbit Nuclear Power Plant. METHODS : This study focused on establishing disaster prevention measures centered on Gwangju Metropolitan City in the event of a major accident such as a radioactive leak at the Hanbit Nuclear Power Plant. Simulations were conducted assuming a major accident such as a radioactive leak, measures to improve resident protection were established by calculating the arrival time of radioactive materials and radiation dosage in the Gwangju area in the event of a nuclear power plant accident, and on-site response action manuals were supplemented in response to a radioactive leak. RESULTS : This study considered the concerns of local residents due to the Fukushima nuclear power plant accident and the Hanbit nuclear power plant failure, conducted a simulation to derive the impact on Gwangju Metropolitan City, and examined the effectiveness of an on-site response manual for radioactive leaks to derive improvement measures. CONCLUSIONS : In the event of an accident at the Hanbit Nuclear Power Plant in Gwangju Metropolitan City, insufficient portions of the on-site response action manual should be supplemented, and close cooperation with local governments within the emergency planning area should be ensured to respond to radioactive disasters. Therefore, based on the revised on-site response action manual for radioactive leaks, close cooperation and a clear division of roles among local governments will enable effective resident protection measures to be implemented in the event of a radioactive disaster.

This study aims to propose an improvement of fire safety management plans for buildings, such as apartment complexes and schools, within a 10 km radius of industrial complexes. It utilizes an off-site consequence analysis program to reflect the toxic impact on national industrial complexes and surrounding areas. The ALOHA program was utilized to analyze the impact of toxicity due to a hydrogen chloride leak, a hazardous material. The results showed that the area with AEGL-2 and above ranged from 3.1 km to 10 km, the AEGL-3 area ranged from 1.9 km to 7.3 km. The ASET was measured to be between 3 and 24 minutes. Due to the impact of toxicity, it is necessary to prepare fire safety management plans for buildings, such as apartment complexes and schools that are within a 10 km radius from industrial complexes. These safety plans incorporate the hydrogen chloride risk assessment results, ASET, weather conditions, and coordination with the local community.

Korea Atomic Energy Research Institute (“KAERI”) has been developing various studies related to the nuclear fuel cycle. Among them, KAERI was focusing on the pyroprocess, which recycles some useful elements white reducing the volume and toxicity of spent nuclear fuel (SNF). Pyroprocess involves the handling of SNF, which cannot be handled directly by the facility worker. Therefore, SNF is handled and processed through remote handling device within a shielded facility such as a hot cell. Nuclear Facilities with such hot cells are called nuclear fuel cycle facilities, and unlike other facilities, heating, ventilating, and air conditioning (HVAC) system are particularly important in nuclear fuel cycle facilities to maintain the atmosphere in the hot cell and remove radioactive materials. In addition, due to the nature of the pyroprocess, which uses molten salt, corrosion is a problem in air atmosphere, so the process can only be carried out in an inert gas atmosphere. KAERI has a nuclear fuel cycle facility called the Irradiation Material Examination Facility (IMEF), and has built and operated the ACPF inside the IMEF, which operates an inert atmosphere hot cell for the demonstration of the pyroprocess. For efficient process development of the pyroprocess, it is necessary to put the developed equipment into the hot cell, which is a radiationcontrolled area, after sufficient verification in a mock-up facility. For this purpose, the ACPF mock-up facility, which simulates the system, space, and remote handling equipment of the ACPF, is operated separately in the general laboratory area. The inert gas conditioning system of the ACPF consists of very complex piping, blowers, and valves, requires special attention to maintenance. In addition, if there is a small leak in the piping within these valves or piping, radioactive materials can be directly exposed to facility workers, so continuous monitoring and maintenance are required to prevent accident. In this study, the applicability of acoustic emission technology and ultrasonic technology for leak detection in the inert gas conditioning system of ACPF mock-up facility was investigated. For this purpose, new bypass pipes and valves were installed in the existing system to simulate the leakage of pipes and valves. Acoustic emission sensors are attached directly to pipes or valves to detect signals, while ultrasonic sensors are installed at a distance to detect signals. The optimal parameters of each technology to effectively suppress background noise were derived and, and the feasibility of identifying normal and abnormal scenarios in the system was analyzed.

In light of recent social concerns related to issues such as water supply pipe deterioration leading to problems like leaks and degraded water quality, the significance of maintenance efforts to enhance water source quality and ensure a stable water supply has grown substantially. In this study, scan statistic was applied to analyze water quality complaints and water leakage accidents from 2015 to 2021 to present a reasonable method to identify areas requiring improvement in water management. SaTScan, a spatio-temporal statistical analysis program, and ArcGIS were used for spatial information analysis, and clusters with high relative risk (RR) were determined using the maximum log-likelihood ratio, relative risk, and Monte Carlo hypothesis test for I city, the target area. Specifically, in the case of water quality complaints, the analysis results were compared by distinguishing cases occurring before and after the onset of "red water." The period between 2015 and 2019 revealed that preceding the occurrence of red water, the leak cluster at location L2 posed a significantly higher risk (RR: 2.45) than other regions. As for water quality complaints, cluster C2 exhibited a notably elevated RR (RR: 2.21) and appeared concentrated in areas D and S, respectively. On the other hand, post-red water incidents of water quality complaints were predominantly concentrated in area S. The analysis found that the locations of complaint clusters were similar to those of red water incidents. Of these, cluster C7 exhibited a substantial RR of 4.58, signifying more than a twofold increase compared to pre-incident levels. A kernel density map analysis was performed using GIS to identify priority areas for waterworks management based on the central location of clusters and complaint cluster RR data.

Since the time to consider when evaluating leakage of spent fuel dry storage systems is very long, assumptions that continue to leak at the initial leakage rate are too conservative. Therefore, this study developed a dynamic methodology to calculate the change in leakage rate using time-varying variables and apply it to calculate the amount of radioactive leakage during the evaluation period. The developed dynamic methodology was then applied to calculate the leakage radiation source term for a hypothetical dry storage system and used to perform a public dose assessment. When applying the developed dynamic leakage rate evaluation methodology for more accurate confinement evaluation in case of containment damage of dry storage system, it was found that the change of leak rate with time is very insignificant if the hole diameter is small enough, and the leak rate decreases rapidly with time when a hole with a certain diameter or larger occurs. In the case of the accident condition, except when the hole is very large, it corresponds to the chocked flow condition, and the leak rate decreases rapidly as soon as the internal pressure is sufficiently lowered to enter the molecular and continuum flow region. In the case of a small hole diameter, the leakage volume is very small, so even if the dynamic methodology is applied, the evaluation results are not different from the case where the initial leakage rate continues, and when the hole diameter exceeds a certain value, the internal pressure drops according to the leakage volume, and the leakage rate decreases significantly. As a result of evaluating the dose to residents by applying the calculated radiation source term, it was confirmed that the dose criteria was exceeded when a hole with a diameter of about 4 μm occurred under off-normal conditions, and the dose standard was exceeded under accident conditions when a chocked flow occurred between the diameter of the hole and 2-3 μm, resulting in a rapid increase in the dose. The results of this study are expected to contribute to a more accurate evaluation of the confinement performance of storage systems, which will contribute to the design of optimal dry storage systems.

시간영역반사계(TDR)는 케이블의 물리적 결함을 검사하는 기법이며 누수 탐지 분야로의 응용영역을 확대하고 있다. 본 연구는 시간영역반사계 기법을 활용하여 선박 기관실 해수 배관의 누설 감지용 케이블형 센서를 개발하였다. 케이블 센서의 형상은 꼬임형상과 흡습부재를 이용하여 제작하였으며 개발된 센서의 누수 감지 여부와 위치 탐지 가능성을 확인하였다. 개발된 센서는 실제 배관 시험 장치 에 부착하여 평가하였으며 해수 누설에 따른 다양한 TDR 신호를 취득하였다. 센서는 꼬임횟수, 피복 두께를 변수로 하여 제작하였으며 TDR 신호에 미치는 효과를 분석하였다. 실험 결과, 꼬임형 센서는 평행한 띠 형상의 센서에 비해 평활한 신호 취득이 가능하였으며 최적 꼬임 횟수는 단위길이 당 10회 이상인 것으로 나타났다. 절연 피복두께의 경우 적정 민감도 확보가 가능한 절연 피복부재의 두께는 도선 직경의 80%~120%로 확인되었다. 누수 위치 추정을 위해 회귀분석 실시 결과, 결정계수는 0.9998로 실제 누설 위치와 높은 상관관계를 나타 내었다. 결과적으로 제안된 TDR 기반의 누수 감지용 꼬임형 센서는 해수 배관 시스템의 누수 감시 센서로의 충분한 적용성을 확인하였다.

In this study, a method of leakage detection was proposed to locate leak position for a reservoir pipeline valve system using wavelet coherence analysis for an injected pressure wave. An unsteady flow analyzer handled nonlinear valve maneuver and corresponding experimental result were compared. Time series of pressure head were analyzed through wavelet coherence analysis both for no leak and leak conditions. The leak information can be obtained through either time domain reflectometry or the difference in wavelet coherence level, which provide predictions in terms of leak location. The reconstructed pressure signal facilitates the identification of leak presence comparing with existing wavelet coherence analysis.

This paper suggests a nonlinear pressure consideration scheme through an unsteady pipe network analyzer for leakage detection with a portable pressure wave generator. In order to evaluate the performance of a proposal scheme, linear input pattern has been simulated and experiments had been carried out under both no leakage and one leakage conditions in a reservoir-pipeline-valve system. This method using portable pressure wave generator showed that a leakage can be detected from a reflection where a leakage is originated through time domain analysis. Meaningful similarity in pressure response between nonlinear input pattern and experimental results were found both no leakage and a leakage conditions.

The purpose of this study is to develop and apply an oil leak detector using a capacitive sensor to detect oil leak in hydraulic equipment. The developed oil leak detector consists of a sensor and a sensing circuit. The sensor is designed using the difference in the permittivity of air and oil to change the capacitance, and the sensing circuit is composed of a charge amplifier and rectifier circuit. The sensing device is made of a PCB module to output the DC analog signal. In this study, this oil detector was installed in a cyclic pressure tester for evaluating valve life and was applied to detect the leakage of the test valve. It can also be applied to detecting the oil leakage of various hydraulic types of equipment and reduce maintenance costs by preventing large leakage of hydraulic oil.

In this study, the leak signal was measured by using an accelerometer to analyze the basic data and methodology for the development of the leak point estimation method in the water supply pipe. The measured results were analyzed by frequency analysis and cross-correlation analysis for leakage signals, and the error range was compared and analyzed with the actual leak point distance. As a result, it was confirmed that the vibration intensity due to leakage from the water leakage point was attenuated according to the distance. In the case of the ductile iron casting used in the experiment, the intensity of the signal at the 945 Hz, 1,500 Hz, 2,300 Hz band was increased with the change of the pressure in the pipe at 4mm of leakage hole. Also, it was confirmed that as the water pressure increases, the intensity of the leak signal increases but the similarity of the signal decreases. The results of this study confirm that the accelerometer sensor can be used efficiently for leak detection and it can be used as a basic data for the analysis for the development of leak point estimation method in the future.

As the chemical industry becomes more advanced, the awareness of chemical accidents is rising, and legal systems for chemical safety management are strengthened. In this study, quantitative risk assessment of liquid chlorine leak was conducted. Risk assessment was performed in the order of frequency analysis, consequence analysis, and risk calculation. The individual risk was presented in the form of contour lines. The social risk was expressed by the FN curve. The risk of day and night was in an unacceptable area, so it was required to mitigate risk. Therefore in-building, which could trap the pool, was selected as a risk mitigation measure. As a result of the cost benefit analysis, it was concluded that this measure should be reasonably implemented.

A real scale leakage test facility was developed to study the leak signal characteristics of water supply pipelines, and then leak tests were carried out. The facility was designed to overcome the limited experimental circumstances of domestic water supply pipeline experimental facilities. The length of the pipeline, which was installed as a straight line, is 280m. Six pipes were installed on a 70m interval with different pipe material and diameters that are DCIP(D200, D150, D100, D80), PE(D75) and PVC(D75).The intensity of the leakage is adjusted by changing the size of the leak hole and the opening rate of ball valve. Various pressure conditions were simulated using a pressure reducing valve.To minimize external noise sources which, deteriorate the quality of measured leak signal, the facility was built at a quiet area, where traffic and water consumption by customers is relatively rare. In addition, the usage of electric equipment was minimized to block out noise and the facility was operated using manual mode. From the experimental results of measured leakage signal at the facility, it was found that the signal intensity weakened and the signal of high frequency band attenuated as the distance from the water leakage point increased.

In this study, the performance experiment was conducted to compare the permeate flux of hollow fiber Vacuum Membrane Distillation module according to leak problem between module housing and membrane bundle. For the permeate flux performance experiment of the two Vacuum Membrane Distillation modules, the Lab-scale experimental equipment was built in the capacity of 1㎥/day. The performance test of the two Vacuum Membrane Distillation modules were analyzed according to the feed water conditions. As a result, it was analyzed that the leak VMD module decreased about 14% of permeate flux than normal VMD module.

외상으로 인한 혈액담즙증은 드물지 않게 보고되고 있고 경피경간 경로를 이용한 담도내시경이나 배액술 등에 의한 의인성 손상이 증가하고 있다. 그러나 담도스텐트 제거에 따 른 대량의 혈액담즙증의 보고는 매우 드물다. 본 증례는 복부 외상으로 간엽절제술을 받은 환자에서 발생한 담즙 누출을 치료하기 위해 삽입한 담도 스텐트를 제거하면서 혈액담 즙증이 대량 출혈로 악화된 사례이다. 간외상 수술 후 담즙 누출로 플라스틱 담도 스텐트 삽입 후 호전 중에 혈액담즙증 및 담도염 발생으로 스텐트 교체 목적으로 제거하였으나 제 거하자마자 대량의 활동성 혈액담즙증으로 악화되었다. 수술 후의 담즙 누출로 인한 주변조직 손상 및 삽입된 담도 스 텐트로 인한 자극과 제거시의 손상이 원인이 될 수 있을 것 으로 생각된다. 치료는 대량 출혈로 내시경 시야가 확보되지 않아 응급 혈관조영술로 지혈술을 시행하였다. 따라서 복부 외상 환자나 수술 환자에서 담즙 누출 후 담도 배액 스텐트 는 일반적으로 시행되는 효과적인 치료 방법이나 혈액담즙 증 및 합병증으로 담도 스텐트를 교체할 때 주변 담도나 혈 관계의 합병증 유무에 대한 사전 검사를 시행하고 스텐트 제거시에도 주의를 요한다.

충전과 방전이 빈번히 발생하는 축전지의 사용수명을 늘리고 안정적인 사용을 위해서는 과 방전을 방지하는 것이 가장 중요한 요인중 하나이다. 축전지의 건강상태를 파악하는 방법에는 여러 가지로 연구가 진행되고 있으며, 그 중에서도 본 논문에서는 가장 간단하게 축전지의 상태를 파악할 수 있는 단자전압을 이용하는 방법을 활용하여 축전지의 잔존용량을 파악하였다. 일정 전압 이하로 축전지의 전압이 떨어지지 못하도록 간단하게 비교기를 이용하여 과 방전이 되지 못하도록 설계 제작하였다. 상수도 시설이 없는 장소의 저수조탱크의 물 소독을 목적으로 제작된 태양광발전을 응용한 소독약 자동 주입장치의 축전지에 설계한 회로를 제작 설치하여 그 동작실험을 하고 그 유용함을 확인하였다.