• 제목/요약/키워드: power plant modeling

검색결과 375건 처리시간 0.028초

국내 원자력발전소의 공기 압축기실에서 윤활유 화재의 위험성 분석을 위한 FDS의 활용 (Application of FDS for the Hazard Analysis of Lubricating Oil Fires in the Air Compressor Room of Domestic Nuclear Power Plant)

  • 한호식;황철홍;백경록;이상규
    • 한국안전학회지
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    • 제31권2호
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    • pp.1-9
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    • 2016
  • The standard procedure of fire modeling was reviewed to minimize the user dependence, based on the NUREG-1934 and 1824 reports. The hazard analysis of lubricating oil fires in the air compressor room of domestic nuclear power plant (NPP) was also performed using a representative fire model, FDS (Fire Dynamics Simulator). The area ($A_f$) and location of fire source were considered as major parameters for the realistic fire scenarios. As a result, the maximum probability to exceed the thermal damage criteria of IEEE-383 unqualified electrical cables was predicted as approximately 70% with $A_f=1m^2$. It was also found that for qualified electrical cables, the maximum probabilities of exceeding the criteria were 2% and 90% with $A_f=2$ and $4m^2$, respectively. It was concluded that all electrical cables should be replaced with IEEE-383 qualified cables and the dike to restrict as $A_f{\leq}2m^2$ should be installed at the same time, in order to assure the thermal stability of electrical cables for lubricating oil fires in the air compressor room of domestic NPP.

원전용 IC를 위한 CMOS 디지털 논리회로의 내방사선 모델 설계 및 누적방사선 손상 분석 (A Radiation-hardened Model Design of CMOS Digital Logic Circuit for Nuclear Power Plant IC and its Total Radiation Damage Analysis)

  • 이민웅;이남호;김종열;조성익
    • 전기학회논문지
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    • 제67권6호
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    • pp.745-752
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    • 2018
  • ICs(Integrated circuits) for nuclear power plant exposed to radiation environment occur malfunctions and data errors by the TID(Total ionizing dose) effects among radiation-damage phenomenons. In order to protect ICs from the TID effects, this paper proposes a radiation-hardening of the logic circuit(D-latch) which used for the data synchronization and the clock division in the ICs design. The radiation-hardening technology in the logic device(NAND) that constitutes the proposed RH(Radiation-hardened) D-latch is structurally more advantageous than the conventional technologies in that it keeps the device characteristics of the commercial process. Because of this, the unit cell based design of the RH logic device is possible, which makes it easier to design RH ICs, including digital logic circuits, and reduce the time and cost required in RH circuit design. In this paper, we design and modeling the structure of RH D-latch based on commercial $0.35{\mu}m$ CMOS process using Silvaco's TCAD 3D tool. As a result of verifying the radiation characteristics by applying the radiation-damage M&S (Modeling&Simulation) technique, we have confirmed the radiation-damage of the standard D-latch and the RH performance of the proposed D-latch by the TID effects.

Field Programmable Gate Array Reliability Analysis Using the Dynamic Flowgraph Methodology

  • McNelles, Phillip;Lu, Lixuan
    • Nuclear Engineering and Technology
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    • 제48권5호
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    • pp.1192-1205
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    • 2016
  • Field programmable gate array (FPGA)-based systems are thought to be a practical option to replace certain obsolete instrumentation and control systems in nuclear power plants. An FPGA is a type of integrated circuit, which is programmed after being manufactured. FPGAs have some advantages over other electronic technologies, such as analog circuits, microprocessors, and Programmable Logic Controllers (PLCs), for nuclear instrumentation and control, and safety system applications. However, safety-related issues for FPGA-based systems remain to be verified. Owing to this, modeling FPGA-based systems for safety assessment has now become an important point of research. One potential methodology is the dynamic flowgraph methodology (DFM). It has been used for modeling software/hardware interactions in modern control systems. In this paper, FPGA logic was analyzed using DFM. Four aspects of FPGAs are investigated: the "IEEE 1164 standard," registers (D flip-flops), configurable logic blocks, and an FPGA-based signal compensator. The ModelSim simulations confirmed that DFM was able to accurately model those four FPGA properties, proving that DFM has the potential to be used in the modeling of FPGA-based systems. Furthermore, advantages of DFM over traditional reliability analysis methods and FPGA simulators are presented, along with a discussion of potential issues with using DFM for FPGA-based system modeling.

Improvement of the Reliability Graph with General Gates to Analyze the Reliability of Dynamic Systems That Have Various Operation Modes

  • Shin, Seung Ki;No, Young Gyu;Seong, Poong Hyun
    • Nuclear Engineering and Technology
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    • 제48권2호
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    • pp.386-403
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    • 2016
  • The safety of nuclear power plants is analyzed by a probabilistic risk assessment, and the fault tree analysis is the most widely used method for a risk assessment with the event tree analysis. One of the well-known disadvantages of the fault tree is that drawing a fault tree for a complex system is a very cumbersome task. Thus, several graphical modeling methods have been proposed for the convenient and intuitive modeling of complex systems. In this paper, the reliability graph with general gates (RGGG) method, one of the intuitive graphical modeling methods based on Bayesian networks, is improved for the reliability analyses of dynamic systems that have various operation modes with time. A reliability matrix is proposed and it is explained how to utilize the reliability matrix in the RGGG for various cases of operation mode changes. The proposed RGGG with a reliability matrix provides a convenient and intuitive modeling of various operation modes of complex systems, and can also be utilized with dynamic nodes that analyze the failure sequences of subcomponents. The combinatorial use of a reliability matrix with dynamic nodes is illustrated through an application to a shutdown cooling system in a nuclear power plant.

잔사유 분무 연소 해석에 관한 연구 (Combustion Modeling of Vacuum Residue Fuel Sprays)

  • 최찬호;허강열
    • 한국연소학회:학술대회논문집
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    • 한국연소학회 2004년도 제28회 KOSCO SYMPOSIUM 논문집
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    • pp.207-214
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    • 2004
  • Extra heavy vacuum residue oil has advantage as the fuel of a power plant in reducing the cost of power generation. Numerical study is conducted by the KIVA code to understand combustion, heat transfer and flow field characteristics in the test reactor. The combustion model of pulverized coal particles is adopted as the combustion process of extra heavy oil is similar to that of coal. As an initial phase of investigation parametric study is performed with respect to SMD and spray angle of injected spray droplets.

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MSET PERFORMANCE OPTIMIZATION THROUGH REGULARIZATION

  • HINES J. WESLEY;USYNIN ALEXANDER
    • Nuclear Engineering and Technology
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    • 제37권2호
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    • pp.177-184
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    • 2005
  • The Multivariate State Estimation Technique (MSET) is being used in Nuclear Power Plants for sensor and equipment condition monitoring. This paper presents the use of regularization methods for optimizing MSET's predictive performance. The techniques are applied to a simulated data set and a data set obtained from a nuclear power plant currently implementing empirical, on-line, equipment condition monitoring techniques. The results show that regularization greatly enhances the predictive performance. Additionally, the selection of prototype vectors is investigated and a local modeling method is presented that can be applied when computational speed is desired.

A study of predicting irradiation-induced transition temperature shift for RPV steels with XGBoost modeling

  • Xu, Chaoliang;Liu, Xiangbing;Wang, Hongke;Li, Yuanfei;Jia, Wenqing;Qian, Wangjie;Quan, Qiwei;Zhang, Huajian;Xue, Fei
    • Nuclear Engineering and Technology
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    • 제53권8호
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    • pp.2610-2615
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    • 2021
  • The prediction of irradiation-induced transition temperature shift for RPV steels is an important method for long term operation of nuclear power plant. Based on the irradiation embrittlement data, an irradiation-induced transition temperature shift prediction model is developed with machine learning method XGBoost. Then the residual, standard deviation and predicted value vs. measured value analysis are conducted to analyze the accuracy of this model. At last, Cu content threshold and saturation values analysis, temperature dependence, Ni/Cu dependence and flux effect are given to verify the reliability. Those results show that the prediction model developed with XGBoost has high accuracy for predicting the irradiation embrittlement trend of RPV steel. The prediction results are consistent with the current understanding of RPV embrittlement mechanism.

울돌목 시험조류발전소의 수중소음 특성 연구 (Acoustic Characteristics of Underwater Noise from Uldolmok Tidal Current Pilot Power Plant)

  • 고명권;최지웅;이진학;정원무
    • 한국음향학회지
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    • 제31권8호
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    • pp.523-531
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    • 2012
  • 최근 친 환경 발전에 관한 관심이 높아지면서 태양광, 풍력, 조력, 조류 발전에 대한 수요가 점차 증가되고 있다. 이러한 친 환경 발전 방식 중 조석운동에 의한 해수의 흐름을 이용하는 조류발전은 지형적 특성에 의해 강한 조류가 발생하는 지역에서만 사용할 수 있는 특수한 발전 방식이다. 울돌목 해역은 조류 발전이 가능한 매우 강한 조류가 형성되는 지역으로 다른 지역의 해역과 구분되는 특별한 환경을 제공한다. 하지만, 해양에서의 인간의 활동은 수중소음을 야기하여 해양환경에 큰 영향을 미친다. 최근에는 환경영향평가의 중요성이 대두되면서 발전소 가동 시의 소음 특성 분석 및 전파양상 예측에 대한 필요성이 증가하고 있다. 본 연구는 조류발전소의 수중소음 특성을 측정하고 울돌목 해역으로의 전파양상을 모델링 하였다.

3D 유한요소법을 이용한 원전 매설배관 부식결함 탐상기술 개발 (Technology for the Detection of Corrosion Defects in Buried Pipes of Nuclear Power Plants with 3D FEM)

  • 김재원;임부택;박흥배;장현영
    • Corrosion Science and Technology
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    • 제17권6호
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    • pp.292-300
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    • 2018
  • The modeling of 3D finite elements based on CAD data has been used to detect sites of corrosion defects in buried pipes. The results generated sophisticated profiles of electrolytic potential and vectors of current distributions on the earth surface. To identify the location of defects in buried pipes, the current distribution on the earth surface was projected to a plane of incidence that was identical to the pipe locations. The locations of minimum electrolytic potential value were found. The results show adequate match between the locations of real and expected defects based on modeling. In addition, the defect size can be calculated by integrating the current density curve. The results show that the defect sizes were $0.74m^2$ and $0.69m^2$, respectively. This technology may represent a breakthrough in the detection of indirect damage in various cases involving multiple defects in size and shape, complex/cross pipe systems, multiple anodes and stray current.

크리깅 기법 기반 재생에너지 환경변수 예측 모형 개발 (Development of Prediction Model for Renewable Energy Environmental Variables Based on Kriging Techniques)

  • 최영도;백자현;전동훈;박상호;최순호;김여진;허진
    • KEPCO Journal on Electric Power and Energy
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    • 제5권3호
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    • pp.223-228
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    • 2019
  • In order to integrate large amounts of variable generation resources such as wind and solar reliably into power grids, accurate renewable energy forecasting is necessary. Since renewable energy generation output is heavily influenced by environmental variables, accurate forecasting of power generation requires meteorological data at the point where the plant is located. Therefore, a spatial approach is required to predict the meteorological variables at the interesting points. In this paper, we propose the meteorological variable prediction model for enhancing renewable generation output forecasting model. The proposed model is implemented by three geostatistical techniques: Ordinary kriging, Universal kriging and Co-kriging.