• 제목/요약/키워드: Plant Database

검색결과 488건 처리시간 0.024초

Concrete properties prediction based on database

  • Chen, Bin;Mao, Qian;Gao, Jingquan;Hu, Zhaoyuan
    • Computers and Concrete
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    • 제16권3호
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    • pp.343-356
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    • 2015
  • 1078 sets of mixtures in total that include fly ash, slag, and/or silica fume have been collected for prediction on concrete properties. A new database platform (Compos) has been developed, by which the stepwise multiple linear regression (SMLR) and BP artificial neural networks (BP ANNs) programs have been applied respectively to identify correlations between the concrete properties (strength, workability, and durability) and the dosage and/or quality of raw materials'. The results showed obvious nonlinear relations so that forecasting by using nonlinear method has clearly higher accuracy than using linear method. The forecasting accuracy rises along with the increasing of age and the prediction on cubic compressive strength have the best results, because the minimum average relative error (MARE) for 60-day cubic compressive strength was less than 8%. The precision for forecasting of concrete workability takes the second place in which the MARE is less than 15%. Forecasting on concrete durability has the lowest accuracy as its MARE has even reached 30%. These conclusions have been certified in a ready-mixed concrete plant that the synthesized MARE of 7-day/28-day strength and initial slump is less than 8%. The parameters of BP ANNs and its conformation have been discussed as well in this study.

원전 콘크리트 구조물의 장기내구성능 평가 (Long-Term Performance of Safety Related Concrete Structures in Nuclear Power Plants)

  • 윤의식;백용락;임재호;정연석;최강룡
    • 한국콘크리트학회:학술대회논문집
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    • 한국콘크리트학회 2006년도 추계 학술발표회 논문집
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    • pp.237-240
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    • 2006
  • Almost 30 years have been passed since the first nuclear power plant was operated in Korea. Many studies have been actively conducted from the early 1990's in order to develop the deterioration management system for concrete structures in NPPs(Nuclear Power Plants) accordingly. Base on these studies, a systematic deterioration management program has developed and operated since 1997. According to this program, systematic inspections to provide database and evaluation were periodically performed (every overhaul at intervals of $12{\sim}18$ month and every five years). Accumulated deterioration database was usefully utilized for the NPP PSR (Periodic Safety Review). In this paper, the long-term durability and integrity of Kori 1,2 NPP concrete structures which are the oldest ones in Korea were evaluated based on the precise inspection database and regulatory inspection results including compressive strength, depth of carbonation, amount of chlorination and spontaneous potential of reinforcing bar, etc. It was noted that Kori 1,2 NPP structures have not any serious durability problems.

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핵심 구조물의 확률론적 지진취약도 분석: 기술현황 (A State-of-the-Art of Probabilistic Seismic Fragility Analysis of Critical Structure)

  • 조양희
    • 한국지진공학회:학술대회논문집
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    • 한국지진공학회 2000년도 춘계 학술발표회 논문집 Proceedings of EESK Conference-Spring
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    • pp.226-232
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    • 2000
  • Seismic probabilistic risk assessment(RA) rather than deterministic assessment provides more valuable information and insight for resolving seismic safety issues in nuclear power plant design. In the course of seismic PRA seismic fragility analysis is the most significant and essential phase especially for structural or mechanical engineers. Lately the seismic fragility analysis is taken as a useful tool in general structural engineering as well. A systemized and synthesized procedure or technology related to seismic fragility analysis of critical industrial facilities reflecting the unique experiences and database in Korea is urgently required. This paper gives a state-of-the-art reviews of PRA and briefly summarizes the technologies related to PRA and seismic fragility analysis before developing an unique technology considering characteristics of Korean database. Some key items to be resolved theoretically or technically are extracted and presented for the future research.

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디지털 정보표시 환경의 지침 기반 평가 기술 (Guideline-based Evaluation of Human Machine System Environment with the Advanced Information Display)

  • 차우창
    • 대한인간공학회지
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    • 제26권1호
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    • pp.99-102
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    • 2007
  • The analog typed interface of main control room in nuclear power plant(NPP) is gradually being replaced to the one suitable for the digital environment. SKN 3,4 is currently developed in such a way to employ digitalized displays and controls such as computerized procedure system(CPS), large display panel(LDP), and Soft control. The main control room (MCR) of the SKN3, 4 was designed based on the human factors guidelines, which somehow lack of the confidence for the rapidly the developed guidelines needs to extend to the one to apply for the total digital environment including task environment, hardware and workstation. In order to achieve the research objectives, tremendous guidelines and technical papers related to evaluation issues of digital environment has been collected, analyzed and transformed to electric database forms and then built on database management system to retrieve the appropriate isues for the practical usage of evaluators-in-field.

사출 성형기 Barrel 온도에 관한 퍼지알고리즘 기반의 고장 검출 및 진단 (Fault Detection and Diagnosis based on Fuzzy Algorithm in the Injection Molding Machine Barrel Temperature)

  • 김훈모
    • 제어로봇시스템학회논문지
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    • 제9권11호
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    • pp.958-962
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    • 2003
  • We acquired data of injection molding machine in operation and stored the data in database. We acquired the data of injection molding machine for fault detection and diagnosis (FDD) continuously and estimated the fault results with a fuzzy algorithm. Many of FDD are applied to a huge system, nuclear power plant and a computer numerical control(CNC) machine for processing machinery. But, the research of FDD is rare in injection molding machine compare with computer numerical control machine. We appraise the accuracy of the FDD and the limit of the application to the injection molding machine. We construct the fault detection and diagnosis system based on fuzzy algorithm in the injection molding machine. Data of operating injection molding machine are acquired in order to improve the reliability of detection and diagnosis.

원자력발전소 주제어실내 Critical function mornitoring system의 인간공학적 평가를 위한 체계적 checklist의 개발 (Development of a Systematic Checklist for the Ergonomic Evaluation of the Critical Function Mornitoring System in the Main Control Room of a Nuclear Power Plant)

  • 홍상우;한성호;윤명환;곽지영;이용희
    • 대한인간공학회:학술대회논문집
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    • 대한인간공학회 1997년도 춘계학술대회논문집
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    • pp.72-74
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    • 1997
  • Integration and standardization of the related regulations and guidelines are necessary to evaluate a CFMS in a systematic manner. In this study, a hierachically categorized evaluation checklist was developed by collecting and structuring human factors issues listed in the various regulations, design requirements, and technical report. A PC-based database management system was developed to update and review the evaluation results. Standard interpretation examples, evaluation guidelines, and sample evaluation formats were also designed and integrated into the database system to reduce discrepancy in evaluation.

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Vehicle Waiting Time Information Service using Vehicle Object Detection at Fuel Charging Station

  • Rijayanti, Rita;Muhammad, Rifqi Fikri;Hwang, Mintae
    • Journal of information and communication convergence engineering
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    • 제18권3호
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    • pp.147-154
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    • 2020
  • In this study, we created a system that can determine the number of vehicles entering and departing a charging station in real time for solving waiting time problems during refueling. Accordingly, we use the You Only Look Once object detection algorithm to detect and count the number of vehicles in the charging station and send the data to the Firebase Realtime Database. The result is shown using an Android application that provides a map function with the Kakao Maps API at the user interface side. Our system has an accuracy of 91% and an average response time of 3.1 s. Therefore, this system can be used by drivers to determine the availability of a charging station and to identify the charging station with the least waiting time for charging their vehicle.

공장자동화를 위한 확장 DNC 시스템 (An Extended DNC System for Factory Automation)

  • 김영기;강무진;이재원
    • 대한기계학회논문집
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    • 제18권9호
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    • pp.2297-2311
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    • 1994
  • This paper presents the study on the development of a DNC, system IPIS(Interactive Plant Information System)/DNC, which can manage NC machines and robots as a distributed control method in the machine. processing factory. The IPIS/DNC system is composed of a host computer, satellites and NC machines. A set of software modules are developed on the host computer and the satellites separately. By modularizing each functions of the IPIS/DNC system and using multi-taking method, the functions such as NC program management, NC program distribution, and shop monitoring can be performed on the host computer, and the functions such as NC program transfer to the NC machines, and NC program editing can be performed on the satellites. A Relational database which is linked with job scheduling system is used for IPIS/DNC system.

국내 안전등급 배관에 대한 손상사례 분석 (Piping Failure Analysis In Domestic Nuclear Safety Piping System)

  • 최선영;최영환
    • 대한기계학회:학술대회논문집
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    • 대한기계학회 2003년도 춘계학술대회
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    • pp.617-621
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    • 2003
  • The purpose of this paper is to analyze piping failure trend of safety pipings In domestic nuclear power plants. First, database for the piping failure was constructed with 105 data fields. The database includes plant population data, event data, and service history data. 7 kinds of piping failures in domestic NPPs were investigated. Among the 7 cases, detailed root causes were investigated for 3 cases. The first one is pipe wall thinning in main feedwater pipings of Westinghouse 3 loop type plants. The root cause of the wall thinning was flow accelerated corrosion near welding area. The next one is leak event in chemical and volume control system(CVCS) due to vibration. Some cracks occurred in socket welding area. The events showed that the integrity or socket weld is very vulnerable to vibration. The last one is also a leak event in primary sampling line in Korean standard reactor due to thermal fatigue. Although the structural integrity was not maintained by the events, there was no effect on nuclear safety in the above 3 piping failure eases.

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PDM 구축을 위한 TIM 모듈개발 (Development of TIM Module for Construction PDM)

  • 이승우;송준엽
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2001년도 춘계학술대회 논문집
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    • pp.307-310
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    • 2001
  • In this paper, development of TIM Module for constructing PDM will be introduced. Technical information relevant product data influences cost, quality, precision and productivity. One of the very important feature of product data is organizing not by oneself but very closed to many technical information such as document, file, image and analysis sheet. To manage various technical information, several kinds of management system are used in multi level of production system. PDM and TIM systems are being developed for suitable purpose and are in need of Network technology, Information Technology, Database, sharing and distributing information. Developed TIM system is based on Web environment. By using this system, we can manage systematic technical information and reduce cost for constructing PDM system. And also we will put to practical use another technical information management system for mold plant.

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