• Nuclear Engineering and Technology
• /
• 제53권2호
• /
• pp.466-473
• /
• 2021

Fire protection is one of important issues to ensure safety and reduce risks of nuclear power plants (NPPs). While robust programs to shut down commercial reactors in any fires have been successfully maintained, the concept and associated regulatory requirements are constantly changing or strengthening by lessons learned from operating experiences and information all over the world. As part of this context, it is necessary not only to establish specific fire hazard assessment methods reflecting the characteristics of research reactors and educational reactors but also to make decisions based on advancement encompassing numerical analyses and experiments. The objectives of this study are to address fire simulation in the control room of an educational reactor and to discuss integrity of digital console in charge of main operation as well as analysis results through comparison. Three electrical fire scenarios were postulated and twenty-four thermal analyses were carried out taking into account two turbulence models, two cable materials and two ventilation conditions. Twelve supplementary thermal analyses and six subsequent structural analyses were also conducted for further examination on the temperature and heat flux of cable and von Mises stress of digital console, respectively. As consequences, effects of each parameter were quantified in detail and future applicability was briefly discussed. On the whole, higher profiles were obtained when Deardorff turbulence model was employed or polyvinyl chloride material and larger ventilation condition were considered. All the maximum values considered in this study met the allowable criteria so that safety action seems available by sustained integrity of the cable linked to digital console within operators' reaction time of 300 s.

• 한국안전학회지
• /
• 제26권5호
• /
• pp.41-45
• /
• 2011

The fire event occurred in fire proof zone often causes serious electrical problems such as shorts, ground faults, or open circuits in nuclear power plants. These would be directed to the loss of safe shutdown capabilities performed by safety related systems and equipments The fire event can treat the basic design principle that safety systems should keep their functions with redundancy and independency. In case of a cable fire, operators can not perform their mission properly and can misjudge the situation because of spurious operation, wrong indication or instrument. These would deteriorate the plant capabilities of safety shutdown and make disastrous conditions. In this paper, the cables of the representative nuclear power plant in korea is selected and the cable functional failure temperature by exposed fire using Cable Response to Live Fire(CAROLFIRE) is studied. It is expected that the results are very useful to know the cable failure temperature by exposed fire. We confirmed the safety and integrity of the cable by exposed fire and those results will use the based data of cable exposed fire characteristics.

• 전기학회논문지
• /
• 제62권7호
• /
• pp.987-993
• /
• 2013

Integrity of the control and instrumental cables in nuclear power plant is important to maintain the stability of the nuclear power plants. In order to diagnose the integrity of the cables, the diagnostic methods based on reflectometry have been studied. The reflectometry is a non-destructive method and it is applicable to diagnose the live cables. We introduce a Gaussian enveloped linear chirp reflectometry to diagnose the cables in the nuclear power plants. In this paper, we estimate the instantaneous frequency of the Gaussian enveloped linear chirp signal by using the weighted robust least squares filtering to localize the impedance discontinuities in the class 1E instrumental cable.

• 한국구조물진단유지관리공학회 논문집
• /
• 제28권3호
• /
• pp.66-73
• /
• 2024

사장교에서 케이블 부재는 하중을 전달하는 가장 중요한 부재 중 하나이다. 따라서 사장교의 구조적 상태 및 안정성을 평가하기 위해서는 케이블의 상태를 파악하기 위해 지속적인 모니터링을 수행하는 것이 중요하다. 이러한 모니터링 시스템은 케이블에 부착된 가속도계를 통해 진동을 측정하고 이를 토대로 케이블 장력과 감쇠비를 추정하고, 이를 토대로 케이블의 상태 평가의 기초자료로 활용한다. 이러한 상시 모니터링 시스템은 지속적으로 진동 데이터를 측정하기 때문에 데이터 수집 시스템을 포함한 하드웨어가 안정적이고 전력 효율성이 높아야 한다. 또한 지속적으로 생성되는 대량의 진동 신호들을 사람의 개입을 최소화하며 안정적으로 분석할 수 있는 자율모니터링 시스템이 요구된다. 본 연구에서는 IoT를 활용한 도메인 지식 기반 자율 모니터링 시스템을 개발하였다. 케이블 자율 모니터링 시스템을 구현하기 위한 가장 중요한 요소는 케이블의 장력과 감쇠비의 추정을 위한 진동 신호의 주파수 영역 내 발생하는 첨두의 자동 추정이다. 본 연구에서는 도메인 지식 기반 첨두 자동 추정 알고리즘을 데이터 수집 및 On-Board Processing이 가능한 IoT 시스템에 내장하여 IoT 센서 단에서 Edge computing이 가능한 효율적인 IoT 자율 모니터링 시스템을 구현하였다. 개발된 자율 모니터링 시스템을 국내 사장교에 설치하여 장기간 현장 운영 성능을 평가하였으며, 그 결과 장기 데이터 수신률, 장력 추정의 정확성, 효율성 측면에서 기존 시스템과 비교하여 작동 성능을 확인하고 검증하였다.

• Structural Engineering and Mechanics
• /
• 제78권4호
• /
• pp.403-411
• /
• 2021

Ties are mandated by many design guidelines and codes to prevent the progressive collapse of buildings initiated by local failures. This study develops a model to estimate catenary/cable action capacity and the required ties in continuous reinforced concrete beams to bridge above the potential failed interior columns. The developed model is derived based on virtual work method and verified using test results presented in the literature. Also, parametric investigations are conducted to estimate the required ties in continuous reinforced concrete beams supporting one-way slab systems. A comparison is conducted between the estimated tie reinforcement using the developed model and that provided by satisfying the integrity provisions of the ACI 318-14 (2014) code. It is shown that the required tie reinforcements to prevent progressive collapse using the developed model are obviously larger than that provided by the integrity requirements of the ACI 318-14 (2014) code. It has been demonstrated that the increases in the demanded tie reinforcements over that provided by satisfying ACI 318-14 (2014) integrity provisions are varied between 1.01 and 1.46.

• Structural Monitoring and Maintenance
• /
• 제10권2호
• /
• pp.133-154
• /
• 2023

Obscured structural members are mostly under-evaluated during condition assessment due to lack of visual inspection capability. Insufficient information about the integrity of these structural members poses a significant risk for public safety. Time domain reflectometry (TDR) is a novel approach in structural health monitoring (SHM). Ordinary coaxial cables "as is" without a major modification are not suitable for SHM with TDR. The objective of this study is to propose a practical and cost-effective modification approach to commercially available coaxial cables in order to use them as a "cable sensor" for damage detection with the TDR equipment for obscured structural members. The experimental validation and assessment of the proposed modification approach was achieved by conducting 3-point bending tests of the model piles as a representative obscured structural member. It can be noted that the RG59/U-6 and RG6/U-4 cable sensors expose higher strain sensitivity in comparison with non-modified "as is" versions of the cables used. As a result, the cable sensors have the capability of sensing both the presence and the location of a structural damage with a maximum aberration of 3 cm. Furthermore, the crack development can be monitored by the RG59/U-6 cable sensor with a simple calibration.

• 한국구조물진단유지관리공학회 논문집
• /
• 제13권3호통권55호
• /
• pp.135-144
• /
• 2009

주케이블과 행어로프로 구성된 케이블 시스템은 현수교에서 가장 중요한 부재로서 외부의 하중을 장력을 통해 전달하여 구조물의 안전성을 확보하는 비선형 요소의 부재이다. 장기간 공용된 교량의 케이블 시스템은 유지관리 활동에 따른 보수 및 보강의 영향을 받아 장력의 증가 혹은 변형이 발생하나 정확한 거동파악이 쉽지 않다. 국내 건설된 사장교에서의 케이블은 상시 모니터링 시스템이 개발되어 관리되고 있으나, 현수교의 주케이블에 대해서는 여전히 관리방법 개발이 필요하다. 이를 위해서 본 논문은 약 35년 공용되어온 남해대교에 대해서, 사용년수 증가에 따른 영향과 과거에 수행되었던 보수 및 보강공사가 케이블 시스템에 어떠한 영향을 주었는지를 파악하기 위해 그 동안 조사되었던 케이블의 손상, 행어로프의 장력 측정 결과 및 주 케이블의 형상측량 결과를 통하여 장기적인 거동을 분석하고 주케이블의 장력 변화를 분석하였다.

• 전기학회논문지
• /
• 제60권8호
• /
• pp.1632-1638
• /
• 2011

Electric cables are one of the most important components in a nuclear power plant since they provide the power needed to operate electrical equipment. Despite their importance, cables typically receive little attention since they are considered passive, long-lived components that have been very reliable over the years when subjected to the environmental conditions for which they were designed. The operating experience reveals that a defect of the insulator or poor construction causes the initial failure of cable. However, the number of cable failures increase with plant aging, and these cable failures are occurring within the plants' 40-year licensed period. These cable failures have resulted in plant transients, shutdown, loss of safety functions or redundancy, entries into limiting conditions for operation, and challenges for plant operators. Therefore, diagnosis of MV cable installed in NPPs has become one of the most urgent issues in recent years. In accordance with PSR, condition maintenance for cables is also continuously required. Recently, HFPD tests have been widely performed to diagnose cable in the transmission and distribution cable system. However, on-line HFPD wasn't used in the NPPs because of the danger of plant shutdown, measurement sensitivity and application problems, etc. In this paper, HFPD measurement with portable device was performed to evaluate the integrity of the 4.16kV & 13.8kV cable lines. The test results show that HFPD is highly attractive to the diagnosis of MV cables in NPP by high detection sensitivity on-site.

• Smart Structures and Systems
• /
• 제23권6호
• /
• pp.695-702
• /
• 2019

The number of cable-stayed bridges has been increasing worldwide, causing issues in maintaining the structural safety and integrity of bridges. The stay cable, one of the most critical members in cable-stayed bridges, is vulnerable to wind-induced vibrations owing to its inherent low damping capacity. Thus, vibration mitigation of stay cables has been an important issue both in academia and practice. While a semi-active control scheme shows effective vibration reduction compared to a passive control scheme, real-world applications are quite limited because it requires complicated equipment, including for data acquisition, and power supply. This study aims to develop an Arduino-based integrated cable vibration control system implementing a semi-active control algorithm. The integrated control system is built on the low-cost, low-power Arduino platform, embedding a semi-active control algorithm. A MEMS accelerometer is installed in the platform to conduct a state feedback for the semi-active control. The Linear Quadratic Gaussian control is applied to estimate a cable state and obtain a control gain, and the clipped optimal algorithm is implemented to control the damping device. This study selects the magnetorheological damper as a semi-active damping device, controlled by the proposed control system. The developed integrated system is applied to a laboratory size cable with a series of experimental studies for identifying the effect of the system on cable vibration reduction. The semi-active control embedded in the integrated system is compared with free and passive mode cases and is shown to reduce the vibration of stay-cables effectively.

• Journal of Electrical Engineering and Technology
• /
• 제9권4호
• /
• pp.1369-1374
• /
• 2014

Most accidents of medium-voltage cables installed in nuclear power plants result from the initial defect of internal insulators or the initial failure due to poor construction. However, as the service years of plants increase, the possibility of cable accidents is also rapidly increases. This is primarily caused by electric, mechanical, thermal, and radiation stresses. Recently, much attention is paid to the study of cable diagnoses. To date, partial discharge and Tan${\delta}$ measurements are known as reliable methods to diagnose the aging of medium-voltage cables. High frequency partial discharge measurement techniques have been widely used to diagnose cables in transmission and distribution systems. However, the on-line high frequency partial discharge technique has not been used in the nuclear power plants because of the plant shutdown risk, degraded measurement sensitivity, and application problems. In this paper, the partial discharge measurement with a portable device was tried to evaluate the integrity of the 4.16kV and 13.8kV cable lines. The test results show that the high detection sensitivity can be achieved by the high frequency partial discharge technique. The present technique is highly attractive to diagnose medium voltage cables in nuclear power plants.