• Title/Summary/Keyword: Module Plants

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The Fault Tolerant Evaluation Model due to the Periodic Automatic Fault Detection Function of the Safety-critical I&C Systems in the Nuclear Power Plants (원전 안전필수 계측제어시스템의 주기적 자동고장검출기능에 따른 고장허용 평가모델)

  • Hur, Seop;Kim, Dong-Hoon;Choi, Jong-Gyun;Kim, Chang-Hwoi;Lee, Dong-Young
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.62 no.7
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    • pp.994-1002
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    • 2013
  • This study suggests a generalized availability and safety evaluation model to evaluate the influences to the system's fault tolerant capabilities depending on automatic fault detection function such as the automatic periodic testings. The conventional evaluation model of automatic fault detection function deals only with the self diagnostics, and supposes that the fault detection coverage of self diagnostics is always constant. But all of the fault detection methods could be degraded. For example, the periodic surveillance test has the potential human errors or test equipment errors, the self diagnostics has the potential degradation of built-in logics, and the automatic periodic testing has the potential degradation of automatic test facilities. The suggested evaluation models have incorporated the loss or erroneous behaviors of the automatic fault detection methods. The availability and the safety of each module of the safety grade platform have been evaluated as they were applied the automatic periodic test methodology and the fault tolerant evaluation models. The availability and safety of the safety grade platform were improved when applied the automatic periodic testing. Especially the fault tolerant capability of the processor module with a weak self-diagnostics and the process parameter input modules were dramatically improved compared to the conventional cases. In addition, as a result of the safety evaluation of the digital reactor protection system, the system safety of the digital parts was improved about 4 times compared to the conventional cases.

Development of the High Reliable Safety PLC for the Nuclear Power Plants (고신뢰도 안전등급 제어기기 개발)

  • Son, Kwang-Seop;Kim, Dong-Hoon;Son, Choul-Woong
    • The Transactions of The Korean Institute of Electrical Engineers
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    • v.62 no.1
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    • pp.109-119
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    • 2013
  • This paper presents the design of the Safety Programmable Logic Controller (SPLC) used in the Nuclear Power Plants, an analysis of a reliability for the SPLC using a markov model. The architecture of the SPLC is designed to have the multiple modular redundancy composed of the Dual Modular Redundancy(DMR) and the Triple Modular Redundancy(TMR). The operating system of the SPLC is designed to have the non-preemptive state based scheduler and the supervisory task managing the sequential scheduling, timing of tasks, diagnostic and security. The data communication of the SPLC is designed to have the deterministic state based protocol, and is designed to satisfy the effective transmission capacity of 20Mbps. Using Markov model, the reliability of SPLC is analyzed, and assessed. To have the reasonable reliability such as the mean time to failure (MTTF) more than 10,000 hours, the failure rate of each SPLC module should be less than $2{\times}10^{-5}$/hour. When the fault coverage factor (FCF) is increased by 0.1, the MTTF is improved by about 4 months, thus to enhance the MTTF effectively, it is needed that the diagnostic ability of each SPLC module should be strengthened. Also as the result of comparison the SPLC and the existing safety grade PLCs, the reliability and MTTF of SPLC is up to 1.6-times and up to 22,000 hours better than the existing PLCs.

Structural Safety Evaluation for the Hydraulic Power Unit of Topside Module According to the Movement of Offshore Plant (해양구조물 움직임에 따른 Topside Module의 HPU에 대한 구조안전성 평가)

  • Ryu, Bo-Rim;Lee, Jin-Uk;Kang, Ho-Keun
    • Journal of the Korean Society of Marine Environment & Safety
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    • v.26 no.6
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    • pp.723-731
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    • 2020
  • The design of offshore plants should reflect the various requirements of the owner and the classification society. For a topside module mounted on an of shore structure, the design process is very demanding because of the large spatial constraints and the many requirements related to marine environmental conditions and safety such as the movement of the structure. In this study, the load acting on the hydraulic power unit, which is one of the main equipment in the topside module, was calculated according to the DNVGL rule; the structural safety was evaluated according to each load condition and the structural reliability of the developed product was improved. For structural analysis, MSC software was used, and structural analysis was performed under five load conditions to review structural safety for various movements. The results show that the maximum stress occurred during pitching toward the stern (Load Case 5). The stress level was approximately 85 % of the allowable stress, and the maximum deformation was approximately 5 % of the allowable value. The structural safety was confirmed, and no intermember interference occurred.

Structural Response of Offshore Plants to Risk-Based Blast Load

  • Heo, YeongAe
    • Architectural research
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    • v.15 no.3
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    • pp.151-158
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    • 2013
  • Offshore oil and gas process plants are exposed to hazardous accidents such as explosion and fire, so that the structural components should resist such accidental loads. Given the possibilities of thousands of different scenarios for the occurrence of an accidental hazard, the best way to predict a reasonable size of a specific accidental load would be the employment of a probabilistic approach. Having the fact that a specific procedure for probabilistic accidental hazard analysis has not yet been established especially for explosion and fire hazards, it is widely accepted that engineers usually take simple and conservative figures in assuming uncertainties inherent in the procedure, resulting either in underestimation or more likely in overestimation in the topside structural design for offshore plants. The variation in the results of a probabilistic approach is determined by the assumptions accepted in the procedures of explosion probability computation, explosion analysis, and structural analysis. A design overpressure load for a sample offshore plant is determined according to the proposed probabilistic approach in this study. CFD analysis results using a Flame Acceleration Simulator, FLACS_v9.1, are utilized to create an overpressure hazard curve. Moreover, the negative impulse and frequency contents of a blast wave are considerably influencing structural responses, but those are completely ignored in a widely used triangular form of blast wave. An idealistic blast wave profile deploying both negative and positive pulses is proposed in this study. A topside process module and piperack with blast wall are 3D FE modeled for structural analysis using LS-DYNA. Three different types of blast wave profiles are applied, two of typical triangular forms having different impulse and the proposed load profile. In conclusion, it is found that a typical triangular blast load leads to overestimation in structural design.

An Automatic Diagnosis Methods for Impact Location Estimation

  • Kim, Jung-Soo;Lyu, Joon
    • Journal of IKEEE
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    • v.3 no.1 s.4
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    • pp.101-108
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    • 1999
  • In this paper, a real time diagnostic algorithm for estimating the impact location by loose parts is proposed. It is composed of two modules such as the alarm discrimination module (ADM) and the impact-location estimation module(IEM). First, ADM decides whether the detected signal that triggers the alarm is the impact signal by loose parts or the noise signal. Second, IEM by use of the arrival time method estimates the impact location of loose parts. In order to validate the application of this method, the test experiment with a mock-up (flat board and reactor) system is performed. The experimental results show the efficiency of this algorithm even under high level noise and potential application to Loose Part Monitoring System (LPMS) for improving diagnosis capability in nuclear power plants.

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A Study on the Design and Control Characteristics for Optimum Operation of the PV System-based ESS (PV System 기반 ESS의 최적운전을 위한 설계 및 제어 특성에 관한 연구)

  • Cha, Insu;Park, Jongbok;Jung, Gyeonghwan
    • Journal of the Korean Solar Energy Society
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    • v.36 no.5
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    • pp.19-30
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    • 2016
  • In this study, realize voltage regulation $220Vac{\pm}10%$ or less, frequency fluctuation $60Hz{\pm}1%$ or less over the independent operation and grid-connected operation technologies for power stabilization relates to the ESS designed and manufactured in conjunction with solar installations and solar to compensate the output reduction due to the polarization of the solar module through the polarization prevention technology for preventing the optical module efficiency is lowered, in conjunction with the BMS inverter efficiency was more than 92%, more than 90% of the charging efficiency to the target. This study was designed in conjunction with the ESS solar power plants, grid-connected operation and independent operation, Peak-Cut, it can stabilize the grid via the Peak-Shifting operation

Workers' Possible Exposure Hazards in Solar Energy Industries (결정질 실리콘 기반 태양광산업에서의 근로자노출 가능 유해인자)

  • Jang, Jae-Kil;Park, Hyunhee
    • Journal of the Korean Solar Energy Society
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    • v.33 no.5
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    • pp.24-33
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    • 2013
  • Renewable energy industries, including sola cell plants, has been ever increasing ones for reducing fossil fuel consumption and strengthening national energy policy. In this paper we tried to identify occupational health hazards in solar cell-related industries operated in Korea. Poly silicon, silicon ingot and wafer, solar cell and module are major processes for producing solar cells. Poly silicon operations may cause hazards to workers from metal silicon, silanes, silicon, hydro fluoric acid and nitric acid. Solar cells could not be constructed without using metals such as aluminum and silver, acids such as hydrofluoric acid and nitric acid, bases such as sodium hydroxide and potassium hydroxide, and solvent and phosphorus chloride oxide. Workers in module assembly process may exposed to isopropanol, flux, solders that contain lead, tin and/or copper. To prevent occupational exposure to these hazards, it is essential to identify the hazards in each process and educate workers in industries with proper engineering and administrative control measures.

An Automatic Diagnosis Method for Impact Location Estimation

  • Kim, Jung-Soo;Joon Lyou
    • 제어로봇시스템학회:학술대회논문집
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    • 1998.10a
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    • pp.295-300
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    • 1998
  • In this paper, a real time diagnostic algorithm fur estimating the impact location by loose parts is proposed. It is composed of two modules such as the alarm discrimination module (ADM) and the impact-location estimation module(IEM). ADM decides whether the detected signal that triggers the alarm is the impact signal by loose parts or the noise signal. When the decision from ADM is concluded as the impact signal, the beginning time of burst-type signal, which the impact signal has usually such a form in time domain, provides the necessary data fur IEM. IEM by use of the arrival time method estimates the impact location of loose parts. The overall results of the estimated impact location are displayed on a computer monitor by the graphical mode and numerical data composed of the impact point, and thereby a plant operator can recognize easily the status of the impact event. This algorithm can perform the diagnosis process automatically and hence the operator's burden and the possible operator's error due to lack of expert knowledge of impact signals can be reduced remarkably. In order to validate the application of this method, the test experiment with a mock-up (flat board and reactor) system is performed. The experimental results show the efficiency of this algorithm even under high level noise and potential application to Loose Part Monitoring System (LPMS) for improving diagnosis capability in nuclear power plants.

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Evaluation of Membrane Module on the Basis of the Domestic Water Quality (국내 먹는 물 수질에 따른 막모듈의 적합성 검토)

  • 권영남;최중구;김종호;탁태문
    • Membrane Journal
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    • v.8 no.4
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    • pp.220-227
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    • 1998
  • Recent data from Environmental department show that some out of 2,000 places surveyed are contaminated by nitrate, ammonia, fluoride, chloride and so forth in excess of the environmental standard-including purification plants, water taps, small water supply systems. In this study, some items which exceed drinking water standard were chosen and their concentrations were made varying from around standard level to around detected maximum concentration. After they permeated through the membrane module sold in the domestic market and made for household water-purifier, the most suitable membranes were selected according to individual water quality of various regions. In addition, the bacterial growth after storage for various days and under various temperatures was examined for the purpose of the effect of the time and temperature on bacterial growth.

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Development of RBI Procedures and Implementation of a Software Based on API Code (II) - Semi-Quantitative Approach (API 기준에 근거한 RBI 절차 개발 및 소프트웨어의 구현 (II) -준정량적 접근법-)

  • Song, Jung-Soo;Shim, Sang-Hoon;Kwon, Jung-Rock;Yoon, Kee-Bong
    • Journal of the Korean Society of Safety
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    • v.17 no.4
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    • pp.110-118
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    • 2002
  • During the last ten years, the need has been increase for reducing maintenance cost for aged equipments are ensuring safety, efficiency and profitability of petrochemical and refinery plants. American Petroleum institute(API) developed a code, API 581 for proposing standard procedures of risk based inspection. Even though the API 581 code covers general RBI procedures, there must be some limitations. In this study, a semi-quantitative assessment algorithm for RBI based on the API 581 code was reconstructed for developing an RBI software. The user-friendly realRBI software is developed with a module for evaluation semi-quantitative risk category using the potential consequence factor and the likelihood factor. Also, inspection planning module for inspection time and inspection method for equipments are included.