• 제목/요약/키워드: Multi-unit accident

검색결과 24건 처리시간 0.019초

PMU 데이터를 이용한 저주파 진동분석 연구 (A Study on the Low Frequency Oscillation Using PMU Measurement Data)

  • 김용학;남수철;고백경;강성범;심관식
    • KEPCO Journal on Electric Power and Energy
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    • 제6권3호
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    • pp.245-252
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    • 2020
  • It is very important to evaluate on/off-line stability to operate the power system stably and economically. Until now, we have continuously secured the operation reliability of the power system through the evaluation of transient, voltage and small signal stability. This paper proposes that it is possible to operate in KWAMS by applying the multi-section analysis and subspace methods and verifying the reliability of the algorithms to directly estimate the dominant oscillation mode of the power system from the signal waveform acquired from the phasor measurement units. In addition, this paper shows that the dominant oscillation mode can be detected from real-time measurement data in power systems. Therefore, if we can monitor the state of the power system in real time, it is possible to avoid a large-scale power outage by knowing the possibility of the power system accident in advance.

Mash-up 분석기술 기반의 아크 고장 검출 알고리즘에 관한 연구 (A Study on Arc Fault Detection Algorithm Based on Mash-up Analysis Technique)

  • 이기연;문현욱;김동우;임용배;최종수
    • 전기학회논문지
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    • 제66권6호
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    • pp.995-1000
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    • 2017
  • In this paper, we present an electrical arc detection algorithm using the mash-up analysis technique which is the core technology for the autonomous electrical safety management system(AESMS) of the multi-unit dwellings. The mash-up analysis technique analyzes the voltage, load current, zero phase current data simultaneously to judge arc faults. In order to develop the arc fault detection algorithm, the characteristics of series arc and parallel arc were analyzed. Also, we propose the mash-up analysis technique that analyzes waveforms of voltage, load current, and zero phase current at the same time. The arc fault detection algorithm was developed using the mash-up analysis technique. The developed algorithm can prevent electrical disasters in an effective way through accident prediction, and it will be used as a basic technology to introduce an autonomous electrical safety management system.

Remaining and emerging issues pertaining to the human reliability analysis of domestic nuclear power plants

  • Park, Jinkyun;Jeon, Hojun;Kim, Jaewhan;Kim, Namcheol;Park, Seong Kyu;Lee, Seungwoo;Lee, Yong Suk
    • Nuclear Engineering and Technology
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    • 제51권5호
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    • pp.1297-1306
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    • 2019
  • Probabilistic safety assessments (PSA) have been used for several decades to visualize the risk level of commercial nuclear power plants (NPPs). Since the role of a human reliability analysis (HRA) is to provide human error probabilities for safety critical tasks to support PSA, PSA quality is strongly affected by HRA quality. Therefore, it is important to understand the underlying limitations or problems of HRA techniques. For this reason, this study conducted a survey among 14 subject matter experts who represent the HRA community of domestic Korean NPPs. As a result, five significant HRA issues were identified: (1) providing a technical basis for the K-HRA (Korean HRA) method, and developing dedicated HRA methods applicable to (2) diverse external events to support Level 1 PSA, (3) digital environments, (4) mobile equipment, and (5) severe accident management guideline tasks to support Level 2 PSA. In addition, an HRA method to support multi-unit PSA was emphasized because it plays an important role in the evaluation of site risk, which is one of the hottest current issues. It is believed that creating such a catalog of prioritized issues will be a good indication of research direction to improve HRA and therefore PSA quality.

Sensitivity analysis of failure correlation between structures, systems, and components on system risk

  • Seunghyun Eem ;Shinyoung Kwag ;In-Kil Choi ;Daegi Hahm
    • Nuclear Engineering and Technology
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    • 제55권3호
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    • pp.981-988
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    • 2023
  • A seismic event caused an accident at the Fukushima Nuclear Power Plant, which further resulted in simultaneous accidents at several units. Consequently, this incident has aroused great interest in the safety of nuclear power plants worldwide. A reasonable safety evaluation of such an external event should appropriately consider the correlation between SSCs (structures, systems, and components) and the probability of failure. However, a probabilistic safety assessment in current nuclear industries is performed conservatively, assuming that the failure correlation between SSCs is independent or completely dependent. This is an extreme assumption; a reasonable risk can be calculated, or risk-based decision-making can be conducted only when the appropriate failure correlation between SSCs is considered. Thus, this study analyzed the effect of the failure correlation of SSCs on the safety of the system to realize rational safety assessment and decision-making. Consequently, the impact on the system differs according to the size of the failure probability of the SSCs and the AND and OR conditions.