원자력 발전소에 설치되는 안전관련 기기의 손상은 심각한 사고로 이어질 수 있으므로 반듯이 지진안전성을 확보하여야 한 다. MCC, Switchgear, Inverter, Battery charger 등의 전기캐비닛은 대표적인 안전관련 기기이다. 대부분의 실험적 연구는 실험대 상기기의 크기와 실험장비의 성능한계 등으로 인하여 주요부품을 대상으로 하며, 실제 원자력발전소에 납품하는 전기캐비닛을 이용하 여 3축 동시가진에 의한 진동대 실험을 수행한 연구는 많지 않다. 따라서 실제기기를 대상으로 3축 진동대 실험을 통하여 내진성능과 한계상태를 직접적으로 평가하기 위한 연구가 필요하다. 이러한 한계상태평가의 주요 목적은 다양한 부품으로 구성된 캐비닛 단위 실 제기기의 임계 가속도 및 고장 모드를 조사하는 것이다. 본 논문에서는 3축 진동대 실험으로 한계상태 내진성능실험을 수행하여 원자 력발전소에 납품되는 것과 동일한 4종의 전기캐비닛들의 한계상태를 분석하였다.

Earthquakes of magnitude 3.0 or greater occur in Korea about 10 times on average yearly, and the number of earthquakes occurring in Korea is increasing. As many earthquakes have recently occurred, interest in the safety of nuclear power plants has increased. Nuclear power plants are equipped with many cabinet-type control facilities to regulate safety facilities, and function maintenance is required during an earthquake. The seismic performance of the cabinet is divided into structural and functional performances. Structural performance can be secured during the design procedure. Functional performance depends on the vibration performance of the component. Therefore, it is necessary to confirm the seismic performance of the components. Generally, seismic performance is confirmed through seismic simulation tests. When checking seismic performance through seismic simulation tests, it is difficult to determine the effect of frequency and maximum acceleration on an element. In this paper, shaking table tests were performed using various frequencies and various maximum accelerations. The seismic performance characteristics of the functions of electrical equipment components were confirmed through tests.

This study proposes a low-cycle fatigue life derived from measurement points on pipe elbows, which are components that are vulnerable to seismic load in the interface piping systems of nuclear power plants that use seismic isolation systems. In order to quantitatively define limit states regarding leakage, i.e., actual failure caused by low-cycle fatigue, in-plane cyclic loading tests were performed using a sine wave of constant amplitude. The test specimens consisted of SCH40 6-inch carbon steel pipe elbows and straight pipes, and an image processing method was used to measure the nonlinear behavior of the test specimens. The leakage lines caused by low-cycle fatigue and the low-cycle fatigue curves were compared and analyzed using the relationship between the relative deformation angles, which were measured based on each of the measurement points on the straight pipe, and the moment, which was measured at the center of the pipe elbow. Damage indices based on the combination of ductility and dissipation energy at each measurement point were used to quantitatively express the time at which leakage occurs due to through-wall cracking in the pipe elbow.

Nuclear power plant’s safety against seismic events is evaluated as risk values by probabilistic seismic safety assessment. The risk values vary by the seismic failure correlation between the structures, systems, and components (SSCs). However, most probabilistic seismic safety assessments idealized the seismic failure correlation between the SSCs as entirely dependent or independent. Such a consideration results in an inaccurate assessment result not reflecting real physical phenomenon. A nuclear power plant’s seismic risk should be calculated with the appropriate seismic failure correlation coefficient between the SSCs for a reasonable outcome. An accident scenario that has an enormous impact on a nuclear power plant’s seismic risk was selected. Moreover, the probabilistic seismic response analyses of a nuclear power plant were performed to derive appropriate seismic failure correlations between SSCs. Based on the analysis results, the seismic failure correlation coefficient between SSCs was derived, and the seismic fragility curve and core damage frequency of the loss of essential power event were calculated. Results were compared with the seismic fragility and core damage frequency of assuming the seismic failure correlations between SSCs were independent and entirely dependent.

Liquid storage tank is one of the major infrastructures and generally used to store gases, drinking and utilizing water, dangerous fluids, fire water and so on. According to the recent reports and experiences, the tank structures are damaged in many earthquakes due to their low energy dissipating capacity. Therefore, many researchers have been tried to know the dynamic properties of the tanks including liquids. However, vary limited experimental studies are carried out using relatively small tank models. In this study, a series of shaking table tests are performed with maximum 2 m cubic rectangular liquid storage tanks made of steel to measure the natural frequency and estimate damping coefficient of impulsive and convective mode of the tanks. Especially, the damping values under different shapes and excitation methods are estimated by logarithmic decrement method and half power band-pass method and compared with current design code and standards such as ASCE 7, Eurocode 8 and NZS. Test results show that the impulsive mode damping is around 2% which is proposed by general standards and codes but the impulsive mode damping is 0.13% average that is slightly lower than the code recommendation.

Many studies are conducted in several fields for fragility analysis of structures or elements which is a probabilistic seismic safety analysis in consideration with uncertainty of seismic loading. It is hard to directly conduct fragility analysis for an infrastructure with social importance due to its size. Therefore, a fragility analysis for an infrastructure mainly conducted in element level or conducted with scaled model built in accordance with similarity law. In this article, fragility analysis for prototype and scaled model of reinforced concrete column was conducted with numerical models which had been updated by the results of shaking table test and pseudo dynamic test. As a result, response stress from the numerical analysis result of prototype model was higher than that from scaled model due to different stiffness ratios between steel and concrete. However, the probability of failure for scaled model was higher than that for prototype model because failure criteria for scaled model was down due to similarity law. Also it was evaluated that probability of failure by using log normal standard deviation of response stresses by spectrum matched accelerograms was more reliable than probability of failure by using existing coefficient of variation normally used.

Tool steels serve a large range of applications including hot and cold workings of metals and injection mouldings of plastics or light alloys. The high speed steels (HSS) are specifically used as cutting tools and wear parts because it has high strength, wear resistance and hardness along with appreciable toughness and fatigue resistance. From the view of HSS microstructure, it can be described as metallic matrix composites formed by a ferrous with a dispersion of hard and wear resistant carbides. The experimental specimens were manufactured using the PIM with T42 powders (50~80 vol.%) and polymer (20~50 vol.%). The green parts were debinded in n-hexane solution at for 8 hours and thermal debinded at an mixed gas atmosphere for 8 hours. Specimens were sintered in high vacuum ( Torr) and various temperatures.

In order to investigate the microstructure and mechanical properties of WC-10 wt% Co insert tool alloy fabricated by PIM (Powder Injection Molding) process, the feedstock of WC-10 wt% and wax used as a kind of binder were mixed together by two blade mixer. After injection molding, the debinding process was carried out by two-steps. First, solvent extraction, in which the binder was eliminated by putting the specimen into normal hexane for 24 hrs at , and subsequently thermal debinding which was conducted at and for 6 hrs in the mixed gas of , respectively. Meantime, in order to compensate the decarburization due to hydrogen, 1.2~1.8% of carbon was added to ensure the integrity of the phase. Finally, the specimens were sintered in vacuum under different temperatures, and the relative density of 99.8% and hardness of 2100 Hv can be achieved when sintered at , even the TRS is lower than the conventional sintering process.

현수교 행어케이블의 장력은 현수교의 상태점검에 있어 중요한 요소이다. 현재 케이블의 장력 추정에는 여러 이론식에 의한 간접적인 방법들이 사용되고 있으며, 케이블의 가속도신호로부터 고유진동수를 측정한 후 고유진동수와 장력과의 관계로부터 케이블의 장력을 추정하는 진동법이 대표적이다. 하지만 운동방정식을 기반으로 하는 진동법은 휨강성의 영향이 큰 짧은 케이블의 장력추정에는 적합하지 않다. 본 논문에서는 10m 미만의 짧은 케이블에 대해서도 전기 가능한 새로운 장력 추정 방법으로 단변분탐색법과, 최적화 기법을 이용한 역해석 기법을 제시하였다. 이론에 대한 검증을 위해 국내에 사용 중인 광안대교 행어케이블을 대상으로, 역해석과 진동법에 의한 추정장력들과 설계장력을 상호 비교하였고, 이를 통해 역해석기법이 길이에 상관없이 장력추정에 유용하다는 결론을 얻었다.

The contact displacement sensors that are currently becoming popular in the shaking table tests are limited depending on their use environments; thus, the reality is that each equipment appears impractical considering its effectiveness and applicability. Therefore, in this study, to verify an algorithm for measuring the displacement responses of a structure using the line detection in the shaking table test, the test was conducted on a reinforced concrete frame.

세계적으로 지진과 같은 자연재해로 인한 대규모 피해가 증가하고 있다. 다양한 연구를 통하여 건물에 대한 내진성능은 확보되었으나, 비구조요소의 내진성능 확보 미흡으로 인하여 인명 피해 및 경제적 손실이 발생하고 있다. 비구조요소는 구조물에 설치되는 위치가 다양하고, 구조물의 위치에 따라 발생하는 진동특성이 다르므로 구조물의 위치별 응답스펙트럼이 필요하다. 또한 구조물의 형식과 구조물이 설치되는 위치에 따라 구조물에 발생하는 응답스펙트럼이 다르게 발생한다. 따라서 응답스펙트럼의 선정이 중요하므로 비구조요소에 작용하는 응답스펙트럼을 도출할 수 있는 명확한 방법이 필요하다. 본 논문에서는 응답스펙트럼을 도출하는 방법을 제안하였으며, 제안한 방법으로 국내에서 발생 가능한 지반응답스펙트럼과 구조시스템을 선정하여 구조해석을 수행하였다. 또한, 간단한 수식으로 응답스펙트럼을 도출하는 방법을 제안함으로서, 비구조요소의 내진시험에 필요한 응답스펙트럼을 생성할 수 있도록 하였다.

In the shaking table test, contact displacement sensors are widely being applied to a structure for measuring the displacement responses, but difficulties may arise depending on the condition of the structure. Moreover, the test uneconomically needs temporary facilities for installing sensors and supplementary equipment for saving the displacement responses of a structure. The contact displacement sensors that are currently becoming popular in the shaking table tests are limited depending on their use environments; thus, the reality is that each equipment appears impractical considering its effectiveness and applicability. Therefore, in this study, to verify an algorithm for measuring the displacement responses of a structure using the vision-based system in the shaking table test, the various tests were conducted.

근접방사선치료는 일반적으로 외부방사선치료와 병행하여 수행되고 치료단계가 매우 복잡하며 이로 인 해 방사선 사고가 발생될 수 있다. 본 연구에서는 이를 해결하기 위해 근접방사선치료에 사고유형과 영향 분석(Failure mode and effects analysis, FMEA) 방법을 적용하여 프로세스 맵을 구성하고 이를 기반으로 각 치료단계에 대한 위해도를 산출하였다. 프로세스 맵은 “외래 및 진료”와 “근접방사선 모의치료”, “CT 모의 치료”, “근접방사선치료계획”, “방사선치료”로 총 5단계로 구성하였으며, 각 치료단계를 세분화하여 세부단 계를 작성하였다. 위해도를 산출하기 위해 의사와 의학물리사, 선량설계사, 방사선사, 간호사가 참여하여 세부단계마다 발생빈도와 심각도, 불검출도를 평가하였다. 전반적으로 프로세스 맵은 각 치료단계마다 환 자 신원 확인 절차가 우선적으로 수행되며, 이는 다른 환자로 오인하여 서로 다른 치료계획이 수립되어 방 사선사고가 발생될 우려가 있다. 프로세스 맵을 기반으로 작성한 세부단계에 대해 위해도를 평가한 결과, 전반적으로 “외래 및 진료”와 “근접방사선치료계획” 과정이 높은 위해도로 평가되었다. 직종마다 평가한 위해도는 서로 다른 경향을 보였으며, 간호사는 방사선치료를 제외한 모든 과정이 55점 이상의 위해도를 보였으며, “근접방사선 모의치료” 과정이 88.8점으로 가장 높았다. 방사선치료를 수행하는 의료기관마다 치 료단계가 다소 차이가 있으므로 해당 기관에 대한 프로세스 맵을 작성하고 위해도를 산출하여 중점관리 항목을 집중적으로 리스크 관리가 수행되어야 할 것으로 생각된다.

In this study, a vision-based monitoring system was applied to measure the dynamic characteristics of the stay cable. The image was acquired during the day to measure the dynamic characteristics of the stay cable and the image filter processing algorithm was applied to reduce the analytical noise of the image.

In this study, to verify the validity of the dynamic responses of cables with the image processing technique, the lift-off test and vibration method (Vision-based System) were used to measure the cable tensions, and the results were compared and analyzed.