• Nuclear Engineering and Technology
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• 제30권2호
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• pp.164-172
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• 1998

This paper presents the detailed modelling of reactor vessel ledge region for the dynamic analysis of the coupled internals and core model. The dynamic responses due to earthquake and pipe break are calculated using the input motions of reactor vessel taken from Ulchin nuclear power plant units 3 and 4. Two different representations for detailed and simplified models of the RV ledge region are made. The dynamic responses of the reactor internals components are compared between them. Response characteristics are reported and simplified model is suggested for earthquake and pipe break analysis for the future design of the reactor internals.

• 한국전자파학회논문지
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• 제12권2호
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• pp.245-250
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• 2001

전자산업 기술의 발달에 따라 인류는 많은 혜택을 누리고 있다. 그러나 전자제어기 등의 고속화, 저전력화, 소형화됨에 따라 불효전자파에 민감하게 반응하여 시스템의 오동작, 손상 등의 많은 문제점을 야기시키고 있다. 특히 과도성 불요전자파는 광대역특성과 높은 상승 전압을 갖고 있어 그 대책이 어렵다. 따라서, 본 논문에서는 위와 같은 문제점을 해결하기위하여 IEC에서 규정하고 있는 IEC61000-4-4에준하여 10MHz ~ 1.5GHz 대역에서 20 ~ 30 dB이상의 감쇠 특성을 가지는 Break-box 내의 EMC 필터를 설계.제작하였다.

• Steel and Composite Structures
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• 제18권6호
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• pp.1465-1478
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• 2015

The effect of cutting off fibers on transient load in a polymeric matrix composite lamina was studied in this paper. The behavior of fibers was considered to be linear elastic and the matrix behavior was considered to be linear viscoelastic. To model the viscoelastic behavior of matrix, a three parameter solid model was employed. To conduct this research, finite difference method was used. The governing equations were obtained using Shear-lag theory and were solved using boundary and initial conditions before and after the development of break. Using finite difference method, the governing integro-differential equations were developed and normal stress in the fibers is obtained. Particular attention is paid the dynamic overshoot resulting when the fibers are suddenly broken. Results show that considering viscoelastic properties of matrix causes a decrease in dynamic load concentration factor and an increase in static load concentration factor. Also with increases the number of broken fibers, trend of increasing load concentration factor decreases gradually. Furthermore, the overshoot of load in fibers adjacent to the break in a polymeric matrix with high transient time is lower than a matrix with lower transient time, but the load concentration factor in the matrix with high transient time is lower.

• 한국국방경영분석학회지
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• 제36권2호
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• pp.1-10
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• 2010

Learning rate is generally applied to estimate an appropriate production labor cost. Learning effect is obtained from repetitive work during the production period under 3 assumptions ; homogeneous production, same producer, quantity measure in continuous unit. However, production breaks occur frequently in Korean defense industry environment because of budget constraint and annual requirements. In this case previous learning effect can not be applied due to learning loss. This paper proposed the application of learning rate when a production break occurs in Korea defense industry. To obtain a learning loss, we surveyed various learning loss factors for different production breaks(6, 12, 18 months) from 4 defense industry companies. Then, we estimate the first unit labor hours in re-production phase after production break using Anderlohr method and Retrograde method with the result of the survey. This work is the first attempt to show a method which defines and evaluates the learning loss factors in Korean defense industry environment.

• 한국소음진동공학회논문집
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• 제19권12호
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• pp.1252-1259
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• 2009

Due to the international competition and global pressure, the roll speed is increased. However, higher speeds increase the power density in the process as well as the plant's potential to react with vibrations. Under certain operating conditions, vibrations may occur, which again cause chattermarks, strip rupture or coil break fault. The appropriate condition monitoring is needed to improve product quality and availability. The aim of condition monitoring is to reduce maintenance costs, increase productivity and improve product quality. This paper proposes a condition monitoring tool designed for the classification of coil break fault. This method is used to cold rolling mill for faults monitoring based on vibration and motor current signals. The results show that the performance of classification has high accuracy based on experimental work.

• 대한의용생체공학회:의공학회지
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• 제22권2호
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• pp.205-210
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• 2001

결석 파쇄에 ES지 장치가 이용되기 시작한 이래, 장치의 성능 및 장치에서 발생시킨 충격파가 생체에 미치는 영향등에 관한 연구가 다수 행해지고 있다. 그 중의 하나가 충격파가 전달되는 곳에는 항상 거론되는 캐비테이션 문제이다. 본 연구에서는 압전식 ESWL 장치로 대상물을 파쇄한다는 가정하에, 그 때의 매질을 캐비테이션이 미치는 영향과 관련지어 둘로 구분한다. 그것에 따라 각 매질에서의 방사음을 관측하고, 매질에 따른 파쇄효율과의 관계를 분석한 결과를 제시한다. 본 논문의 결과들은 캐비테이션 기포의 발생율이 작은 탈기수쪽이 방사음에 있어서도 분산성이 작고, 파쇄효율면에 있어서도 안정된 점을 확실히 나타내고 있다.

• 한국음향학회지
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• 제19권5호
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• pp.35-40
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• 2000

본 연구에서는 먼저 압전형 쇄석기에 의한 충격파 조사시에 발생하는 파쇄대상물의 진동과 그 때 들려오는 방사음과의 관계에 대하여 검토한다. 다음에 대상물에 있어서의 초점위치와 고유진동과의 관계에 대해서도 조사한 결과를 제시한다. 아울러 동일한 실험을 파쇄가능한 대상물에 시행하여 대상물의 진동과 그 파쇄효율과의 관계에 대해서도 실험적으로 검토한다. 그 결과, 초점위치에 따른 대상물 고유진동의 피크 주파수 파워와 파쇄효율과의 상관성을 명확히 확인할 수 있었다.

• Nuclear Engineering and Technology
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• 제39권4호
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• pp.287-298
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• 2007

As part of the $AP1000^{TM}$ pressurized water reactor design certification program, a series of integral systems tests of the nuclear steam supply system was performed at the APEX-1000 test facility at Oregon State University. These tests provided data necessary to validate Westinghouse safety analysis computer codes for AP1000 applications. In addition, the tests provided the opportunity to investigate the thermal-hydraulic phenomena expected to be important in AP1000 small-break loss of coolant accidents (SBLOCAs). The APEX-1000 facility is a 1/4-scale pressure and 1/4-scale height simulation of the AP1000 nuclear steam supply system and passive safety features. A series of eleven tests was performed in the APEX-1000 facility as part of a U.S. Department of Energy contract. In all, four SBLOCA tests representing a spectrum of break sizes and locations were simulated along with tests to study specific phenomena of interest. The focus of this paper is the SBLOCA tests. The key thermal-hydraulic phenomena simulated in the APEX-1000 tests, and the performance and interactions of the passive safety-related systems that can be investigated through the APEX-1000 facility, are emphasized. The APEX-1000 tests demonstrate that the AP1000 passive safety-related systems successfully combine to provide a continuous removal of core decay heat and the reactor core remains covered with considerable margin for all small-break LOCA events.

• Nuclear Engineering and Technology
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• 제52권5호
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• pp.1051-1065
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• 2020

Safety analysis of nuclear power plant (NPP) especially in accident conditions is a basic and necessary issue for applications and commercialization of reactors. Many previous researches and development works have been conducted. However, most achievements focused on the safety reliability of primary pressure system vessels. Few literatures studied the structural safety of huge concrete structures surrounding primary pressure system, especially for the fourth generation NPP which allows existing of through cracks. In this paper, structural safety reliability of concrete structures of HTR-PM in accidental double-ended break of hot gas ducts was studied by Exceedance Probability Method. It was calculated by Monte Carlo approaches applying numerical simulations by Abaqus. Damage parameters were proposed and used to define the property of concrete, which can perfectly describe the crack state of concrete structures. Calculation results indicated that functional failure determined by deterministic safety analysis was decided by the crack resistance capability of containment buildings, whereas the bearing capacity of concrete structures possess a high safety margin. The failure probability of concrete structures during an accident of double-ended break of hot gas ducts will be 31.18%. Adding the consideration the contingency occurrence probability of the accident, probability of functional failure is sufficiently low.

• KEPCO Journal on Electric Power and Energy
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• 제5권1호
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• pp.11-15
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• 2019

최근 송전전압 격상으로 인해 차단기 또한 정격이 높아지고 있다. 이에 차단부의 전압 정격을 높이기 위한 방법으로 차단부 2개 이상을 직렬로 구성하는 다점절 차단기가 설치되어 운용되고 있다. 다점절 차단기에서 차단부 극간에 설치되는 균압용 콘덴서는 점절간 균등한 전압분배와 초기 과도회복전압을 저감하는 기능을 수행한다. 하지만, 세계적으로 실계통 사용에서 균압용 콘덴서는 기계적인 손상, 절연파괴에 의한 폭발 등 다수의 고장이 발생하고 있어, 이에 대한 원인 규명과 새로운 성능 검증방법에 대한 연구 필요성이 제기 되고 있다. 본 논문에서는 한전 계통에서 주로 발생한 균압용 콘덴서의 절연파괴 원인을 규명하고 이에 대한 제품 성능검증 방법을 제안하고자 한다.