원자력 발전소에서 배관 시스템은 냉각수 및 오염수를 운반하고 생성된 증기를 터빈으로 이동시켜 에너지를 생산하는 중요한 설비이다. 국내에 건설된 원자력 발전소의 가동연수가 증가함에 따라 배관 시스템의 물리적, 기계적 성질의 열화현상은 발생할 수 있으며 이를 경년열화로 정의한다. 배관 시스 템의 경년열화는 재료의 피로, 부식(국부감육), 마모 등과 같은 메커니즘을 통해 발생할 수 있으며 재 료의 강도 및 시스템의 성능 저하와 균열을 야기할 수 있다. 지속적이고 안정적인 에너지 생산을 위해 경제성과 정확도를 고려한 원전 배관 시스템의 손상 감시 기술은 필요하다. 따라서 본 연구는 원전 배 관 시스템의 손상 감시 기술을 개발하기 위한 기초적인 연구로써 배관 시스템의 취약요소로 판단되는 elbow의 국부적인 감육에 따른 거동의 변화를 분석하고자 한다.

PURPOSES : Sprinkler facilities play a crucial role in extinguishing fires in the early stages of a building blaze. Data indicate that more than 96% of fires are suppressed by sprinklers before growing out of control. However, corrosion and pitting of the sprinkler piping can reduce system performance as facilities age. The purpose of this study is to develop an eco-friendly water-soluble corrosion inhibitor to improve the reliability and longevity of sprinkler piping. METHODS : This study compared and analyzed silicate-based sprinkler piping shrinkage agents as corrosion inhibitor against existing commercial options. Tests were conducted to evaluate reactivity with fire extinguishing water, including electrolyzed reduced water and normal water. The anticorrosive performance of the silicate-based corrosion inhibitor was evaluated under various conditions to establish suitability before potential development or commercialization. RESULTS : The new corrosion inhibitor demonstrated eco-friendly performance. In testing, none of the primary four hazardous substances that pose the most risk of harm to the human body (specifically, arsenic (As), lead (Pb), cadmium (Cd), and mercury (Hg)) were detected. The inhibitor effectively reduced corrosion of carbon steel (SPP), with weight loss rates averaging 0.12% and not exceeding 0.27%. For copper (CDA 110) weight loss rates were up to 0.03%. Testing under constant temperature and humidity conditions show that the inhibitor kept weight loss was below 0.002 g, with no significant numerical value for the weight loss rate. Overall, the results indicate the potential for an environmentally-safe corrosion inhibitor. CONCLUSIONS : The optimal silicate-based sprinkler system can provide real-time sensor information such as oxygen saturation, pH concentration, and total dissolved solids (TDS). These metrics are closely related to the aging process. By linking this system with an aging monitoring solution, maintenance costs and safety could be improved over the lifespan of the sprinkler system. The sensors and monitoring capabilities are expected to enhance maintenance efficiency and equipment reliability.

The presence of technological voids in deep geological repositories for high-level radioactive nuclear waste can have negative effects on the hydro-mechanical properties of the engineered barrier system when groundwater infiltrates from the surrounding rock. This study conducted hydration tests along with image acquisition and X-ray CT analysis on compacted Korean bentonite samples, which simulated technological voids filling to investigate the behavior of fracturing (piping erosion) and cracking deterioration. We utilized a dual syringe pump to inject water into a cell consisting of a bentonite block and technological voids at a consistent flow rate. The results showed that water inflow to fill technological voids led to partial hydration and self-sealing, followed by the formation of an erosional piping channel along the wetting front. After the piping channel generated, the cyclic filling-piping stage is characterized by the repetitive accumulation and drop of water pressure, accompanied by the opening and closing of piping channels. The stoppage of water inflow leads to the formation of macro- and micro cracks in bentonite due to moisture migration caused by high suction pressure. These cracks create preferential flow paths that promote longterm groundwater infiltration. The experimental test and analysis are currently ongoing. Further experiments will be conducted to investigate the effects of different dry density in bentonite, flow rate, and chemical composition of injected water.

이번에 제시할 화상 사례 보고는 환자와 검사를 시행하는 방사선사의 부주의로 인한 화상 안전사고가 아니라 환자 가운 의 치수 구별을 하기 위하여 사용한 녹색 염료가 착색된 파이핑 라인에서 발생한 복부 부위 화상 안전사고에 대한 MRI 인공물 영상과 사례를 보고하고자 함이다. 화학 착색염료는 다양한 금속을 사용하여 만들어지고 주로 금속 염화물로 이루 어져 있으며 이번에 화상 사례로 발생한 녹색 염료는 열 전도성이 높은 구리와 크롬, 철 성분이 많이 함유된 염화물이 주로 사용되고 있다. 이러한 화상 안전사고를 막기 위해서는 염료의 성분에 대해서 알아보고 열 전도성이 없는 스펀지나 면으로 된 포 등을 피부와 환자 가운 사이에 끼워 간격을 두어야 할 것이다. 이번 화상 사례는 철저한 검사 전 선별 절차에도 불구 하고 화상 안전사고가 발생할 수 있음을 보여 주고 있으며 MRI 인공물 영상을 확인하여 조치하면 화상 안전사고를 미리 예방할 수 있는 정보로 가치가 있을 것으로 생각된다.

Damage to gas and fire protection piping systems can lead to secondary disasters after an earthquake, so their seismic design is crucial. Accordingly, various types of seismic restraint installations are being devised, and a new suspended piping trapeze restraint installation has also recently been developed in Korea. In this study, a cyclic loading test was performed on the developed trapeze support system, and its performance was evaluated according to ASHRAE 171, the standard for seismic and wind restraint design established by the American Society of Refrigeration and Air Conditioning Engineers (ASHRAE). The three support system specimens did not break or fracture, causing only insignificant deformations until the end of the experiment. Based on the experimentally rated strength and displacement performance, this trapeze support system is expected to control the seismic movement of piping during an earthquake.

Canada’s Pickering Unit 3 was performed a three-stage decontamination from June to August 1989 in preparation for pressure tube replacement. The first step was a reducing CAN-DECON treatment to dissolve the magnetic film inside the reactor, which was applied following partial defueling of the reactor core. The second step was an oxidative dilute alkaline permanganate treatment to remove the chromium-rich oxides of the stainless steel parts. And the final CAN-DECON step was applied continuously after completely removing fuel from the reactor core. In situ pipe gamma-ray spectroscopy techniques were applied to measure radioactivity within feeder piping during various stages of Pickering Unit 3 decontamination. Measurements were performed at a maximum dose rate of 5 mSv/h, and both the detector and the scanned feeder pipe were properly shielded from other neighboring pipes. 60Co was the dominant radionuclide in feeder piping prior to decontamination. And radionuclides 103Ru, 95Zr, 95Nb, 59Fe, 140La and 124Sb were detected. The Co-60 radioactivity was 2.09×105 Bq/cm2 before decontamination and 3.11×103 Bq/cm2 after decontamination in the inlet feeder pipe T18. And in the outlet feeder pipe P21, it is 2.56×104 Bq/cm2 before decontamination and 2.04×103 Bq/cm2 after decontamination.

The electrical connection between zinc metal and iron in contact with water prevents oxidation of iron until all zinc is dissolved, which is called a zinc sacrificial anode phenomenon. In the case of water pipes, zinc is often attached to the outside of the pipe, but examples of mounting zinc inside the pipe to prevent iron corrosion are not well known. Zinc devices sold for water pipes vary in the amount of zinc installed depending on the diameter of the pipe and the conditions of use, but the life of the product is generally expected to be 10-20 years until all zinc dissolves and disappears. Zinc ions dissolved from zinc to water in the pipe react with the calcium carbonate scale generated inside the pipe to consume zinc ions, and it was confirmed that the needle-shaped aragonite was converted into highly crystalline calcium after observing the scale crystal through an electron microscope. In addition, it is estimated that calcium ions of scale are replaced by zinc ions, gradually losing crystallinity, being deintercalated into the pipe, and oxygen in the water is consumed during the dissolution of zinc ions from zinc metals, turning red rust hematite (Fe2O3) into magnetite (Fe3O4). In addition, zinc ions were expected to move hundreds to thousands of meters depending on the diameter of the pipe in the new pipe, but it was confirmed that the travel distance was shortened in the case of pipes with many corrosion products.

배관 시스템은 기체 및 액체 등의 에너지원을 수송하기 위해 사용되며 주로 건물 내부에 설치되거나 지반에 매립되 어 설치된다. 매립된 배관 시스템은 지진이나 지반침하와 같은 큰 상대변위를 받을 수 있으며 이는 배관의 연결부에 손상을 야 기할 수 있다. 벨로우즈는 기하학적 특성으로 축방향 및 회전 변형을 일부 허용한다. 그러므로 벨로우즈 신축관이음을 적용하면 큰 상대변위에 의한 손상을 줄일 수 있는 것으로 예상된다. 하지만 벨로우즈의 성형과정에서 회선의 벽 두께 감소가 발생할 수 있으며 이는 휨 및 인장 성능에 영향을 미칠 수 있다. 본 연구는 단조하중을 받는 벨로우즈 신축관이음의 성능을 분석하기 위 한 실험적 연구를 수행하였다. 또한 단조하중 실험 결과를 바탕으로 벨로우즈 신축관이음의 유한요소모델을 구축하였으며 실험 결과와 비교하여 검증하였다. 검증된 유한요소 모델을 이용하여 회선의 두께 감소에 의한 성능 변화를 분석하였다. 벽 두께 감 소율은 5%, 10%, 15%, 20%, 25%로 가정하였다. 해석 결과 인장 및 휨 하중에 따른 하중-변위 관계의 전체적인 강성과 최대 하 중이 감소하는 것으로 나타났다. 벽 두께 감소율이 25%일 때 인장 및 휨 하중에 따른 최대 하중은 각각 14%, 26% 감소하는 것 으로 나타났다.

Trojan Nuclear Power Plant (NPP), a four-loop PWR designed by Westinghouse and owned by Portland General Electric (PGE), reached its initial threshold in 1975 and was operational until November 1992. PGE received a Possession Only License from the NRC in May 1993. In 1995, limited decommissioning activities began at the Trojan, including the completion of a large components removal project to remove and dispose of four steam generators and pressurizers from the containment building. In April 1996, the NRC approved a plan to dismantling the Trojan NPP and began more aggressive component removal activities. At the end of 1998, part of the radioactive drainage system began to be removed, and embedded piping decontamination and survey activities began. Trojan NPP has more than 8,840 m of contaminated pipelines throughout the power block. Most of Trojan NPP’s contaminated embedded piping can generally be divided into four categories drainage piping, ventilation ducts, buried process piping, and other items. For the Trojan NPP, the complete removal of contaminated and embedded piping without damaging the building would have significantly increased costs due to the structural considerations of the building and the depth of the embedded pipe. Therefore, Trojan NPP has chosen to conduct the Embedded Pipe Remediation Project (EPRP) to clean and in situ survey of most of the embedded piping to meet the Final Site Survey (FSS) acceptance criteria, with much success. This study provides a discussion of EPRP activities in the Trojan NPP, including classification and characterization of affected piping, modeling of proposed contamination acceptance criteria, and evaluation of various decontamination and survey techniques. It describes the decontamination tools, techniques, and survey equipment and the condition of work and cost estimate costs used in these projects. To identify embedded piping and drains at the Trojan NPP, based on frequent site surveys, plan sketches showing an overview of system flow paths and connections and database were developed to identify drain inputs and headers. This approach effort has been a successful method of remediation and site survey activities. The developed database was a valuable asset to the EPRP and a Work Breakdown Structure (WBS) code was assigned to each drains and headers, allowing the embedded piping to be integrated into the decommissioning cost estimation software (Decon. Expert) and schedule, which aided in decommissioning cost estimation. Also, regular database updates made it easy to check the status of the decommissioning project data. The waste system drain at Trojan NPP was heavily contaminated. The goal of the remediation effort is to completely remove all removable contamination and to reduce the fixed contamination below the decided contamination acceptance criteria. Accordingly, Hydrolysis, Media blast, Chemical decontamination and Pipe removal were considered as remediation option. Trojan NPP’s drainage pipe decontamination option did not cause a significant corrosion layer inside the pipe and media blast was chosen as the main method for stainless steel pipe. In particular, the decommissioning owner decontaminates most of the embedded piping in-situ to meet the FSS acceptance criteria for economic feasibility in Trojan NPP. The remaining pipe was filled with grout to prevent leaching and spreading of contamination inside the pipe. In-situ decontamination and survey of most of these contaminated pipes are considered the most cost-effective option.

When a rapid groundwater inflow is introduced from the adjacent rock mass in the early stage of disposal, hydraulic pressure build-up occurs, which may cause piping erosion at the buffer material itself and the interface of the gap-filling material. Such piping erosion in compacted bentonite buffer via interaction between the buffer and the adjacent rock mass may deteriorate the performance of the buffer material. Therefore, it is necessary to understand the conditions and scenarios in which the piping phenomenon around the buffer material occurs for the long-term health of the repository. In this study, laboratory-scale experimental tests of piping erosion in buffer and interfacial rock was introduced. ø 100 mm × 200 mm height compacted bentonite specimens were placed in a cylindrical acetal cell, and the distilled water was continuously injected at a flow rate of 0.068 L/min using a dual syringe pump. The inflow of water was generated from the bottom and side cell of buffer material. During water injection, injected water pressure and amount were measured with visual observation. The results showed that the external saturation of buffer firstly occurs followed by piping crack generation along the wetting front. The additional piping channels were generated and merged with others. As the injection stopped, the swelling and self-sealing behavior of buffer material were observed. Moreover, X-ray CT scanning of the cell was conducted after the piping simulation to analyze the piping channels and saturation depth. The results highlight the piping erosion phenomenon mainly occurs due to the presence of a gap outside the buffer material. Further experimental cases is need to comprehensively understand piping phenomena in buffer material for assessing the long-term stability of underground radioactive waste disposal systems.

밸브의 내부 누설 현상은 밸브의 내부 부품의 손상에 의해 발생하며 배관 시스템의 사고와 운전정지를 일으키는 주요 요인이 다. 본 연구는 버터플라이형 밸브의 내부 누설에 따라 배관계에서 발생하는 음향방출 신호를 이용하여 배관 가동 중 실시간 누설 진단의 가능성을 검토하였다. 이를 위해 밸브의 작동 모드별로 측정한 시간영역의 AE 원시신호를 취득하였으며 이로부터 구축한 데이터셋은 데 이터 기반의 인공지능 알고리즘에 적용하여 밸브의 내부 누설 유무를 진단하는 모델을 생성하였다. 누설 유무진단을 분류의 문제로 정의 하여 SVM 기반의 머신러닝과 CNN 기반의 딥러닝 분류 알고리즘을 적용하였다. 데이터의 특징 추출에 기반한 SVM 분류 모델의 경우, 이 진분류 모델에서 구축된 모델에 따라 83~90%의 정확도를 나타냈으며, 다중 클래스인 경우 분류 정확도가 66%로 감소하였다. 반면, CNN 기반의 다중 클래스 분류 모델의 경우 99.85%의 분류 정확도를 얻을 수 있었다. 결론적으로 밸브 내부 누설 진단을 위한 SVM 분류모델은 다중 클래스의 정확도 향상을 위해 적절한 특징 추출이 필요하며, CNN 기반의 분류모델은 프로세서의 성능 저하만 없다면 누설진단과 밸브 개도 분류에 효율적인 접근방법임을 확인하였다.

Many piping systems installed in the power plant are directly related to the safety and operation of the plant. Various dampers have been applied to the piping system to reduce the damage caused by earthquakes. In order to reduce the vibration of the piping system, this study developed a steel coil damper (SCD) with a straightforward structure but excellent damping performance. SCD reduces the vibration of the objective structure by hysteretic damping. The new SCD damper can be applied to high-temperature environments since it consists of steel members. The paper introduces a design method for the elastoplastic coil spring, which is the critical element of SCD. The practical applicability of the design procedure was validated by comparing the nonlinear force-displacement curves calculated by design equations with the results obtained from nonlinear finite element analysis and repeated loading test. It was found that the designed SCD’s have a damping ratio higher than 25%. In addition, this study performed a set of seismic tests using a shaking table with an existing piping system to verify the vibration control capacity on the piping system by SCD. Test results prove that the SCD can effectively control the displacement vibration of the piping system up to 80%.

배관 시스템은 다양한 산업영역에서 액체 및 기체로 이루어진 에너지를 수송을 담당하는 중요한 비구조요소로 지진과 같은 외부하중에 의해 손상될 경우 누수로 인한 홍수 및 가연성 가스 누출로 인한 화재 등의 2차피해가 발생할 수 있다. 배관 시스템은 구조물 내부에 설치되는 경우도 있으며 지반에 매립되어 설치되는 경우도 있다. 지반에 매립될 경우 지진으로 인한 과도한 상대변위에 의해 연결부의 손상을 초래할 수 있어 종종 벨로우즈 신축이음관을 적용하여 이러한 피해를 저감시킬 수 있다. 따라서 본 연구에서는 벨로우즈 신축이음관의 반복가력 실험을 기반으로 유한요소 모델을 구축 하여 내진성능을 검토하였다. 반복가력실험은 ±28mm 변위에서 최대 ±123.4mm까지 증가시켜 변위제어를 통해 수행되었으며 추가적으로 유한요소 모델의 신뢰성을 높이기 위해 벨로우즈 배관에 사용된 재료인 STS304의 재료 인장실험을 수행하여 탄성계수 및 항복응력을 결정하였다. 에너지 소산량과 등가 점성 감쇠를 비교하여 개발된 모델의 타당성을 검토하였으며 적용되는 변위가 커짐에 따라 최대 10% 미만의 오차가 발생하여 실험 및 해석결과가 잘 일치하는 것으로 나타났다.

In the dismantling process of a reactor coolant system (RCS) piping, a radiation protection plan should be established to minimize the radiation exposure doses of dismantling workers. Hence, it is necessary to estimate the individual effective dose in the RCS piping dismantling process when decommissioning a nuclear power plant. In this study, the radiation exposure doses of the dismantling workers at different positions was estimated using the MicroShield dose assessment program based on the NUREG/CR-1595 report. The individual effective dose, which is the sum of the effective dose to each tissue considering the working time, was used to estimate the radiation exposure dose. The estimations of the simulation results for all RCS piping dismantling tasks satisfied the dose limits prescribed by the ICRP-60 report. In dismantling the RCS piping of the Kori-1 or Wolsong-1 units in South Korea, the estimation and reduction method for the radiation exposure dose, and the simulated results of this study can be used to implement the radiation safety for optimal dismantling by providing information on the radiation exposure doses of the dismantling workers.

In this study, by using a system analysis program(Fluid Flow), the correlation between the location where cladding damage occurs frequently inside the power plant seawater pipe and flow characteristics is analyzed, and the root cause and improvement plan are reviewed. As a result, it was confirmed that a high flow velocity occurred in the backwash piping(7.64m/s) and the front and rear ends of the flow control valve(5.93m/s). In addition, it was confirmed that cavitation occurs when the seawater level decreases below the saturated water vapor pressure at the rear end of the orifice. These areas are locations where the internal cladding damage occurs frequently in power plants, and the main cause of damage is considered to be excessive flow velocity and cavitation in the pipe. In order to solve this problem, improvement method such as installation of backwash pipe orifices, change of pipe shape at the front and rear end of flow control valve, and change of orifice type were derived.

원자력 발전소에 지진격리장치를 설치하여 내진성능을 향상시킬 수 있다. 그러나 지진격리장치의 적용으로 지반과 구조물 사이에서 큰 상대 변위가 발생하게 된다. 따라서 지진격리된 구조물과 일반 구조물을 연결하는 연결배관시스템의 경우 지진리스크가 증가할 수 있다. 따라서 이러한 배관시스템의 지진취약도를 분석할 필요가 있다. 본 연구에서는 지진취약도 분석 을 위해 지진격리된 APR1400 원자력발전소와 주증기관을 대상으로 지진취약도를 분석하였다. 주증기관은 지진격리된 nuclear island의 보조 건물과 터빈 건물을 연결하는 인터페이스 배관이다. 지진취약도 분석을 위한 파괴모드는 누출관통균열로 정의하였다. 누출은 실험결과와 수치해석을 통해 손상지수로 정량화하여 취약도 분석을 위한 파괴기준으로 사용하였다. 파괴기준의 변동에 의한 취약도 곡선의 변동성을 확인하기 위하여 손상지수의 최솟값, 최댓값, 평균값 및 중앙값을 파괴기준으로 하여 지진취약도 곡선을 작성하였다.