• Title/Summary/Keyword: SACADA

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SACADA and HuREX part 2: The use of SACADA and HuREX data to estimate human error probabilities

  • Kim, Yochan;Chang, Yung Hsien James;Park, Jinkyun;Criscione, Lawrence
    • Nuclear Engineering and Technology
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    • v.54 no.3
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    • pp.896-908
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    • 2022
  • As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), the primary role of human reliability analysis (HRA) is to provide credible estimations of the human error probabilities (HEPs) of safety-critical tasks. In this regard, it is vital to provide credible HEPs based on firm technical underpinnings including (but not limited to): (1) how to collect HRA data from available sources of information, and (2) how to inform HRA practitioners with the collected HRA data. Because of these necessities, the U.S. Nuclear Regulatory Commission and the Korea Atomic Energy Research Institute independently developed two dedicated HRA data collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) and HuREX (Human Reliability data EXtraction), respectively. These systems provide unique frameworks that can be used to secure HRA data from full-scope training simulators of NPPs (i.e., simulator data). In order to investigate the applicability of these two systems, two papers have been prepared with distinct purposes. The first paper, entitled "SACADA and HuREX: Part 1. The Use of SACADA and HuREX Systems to Collect Human Reliability Data", deals with technical issues pertaining to the collection of HRA data. This second paper explains how the two systems are able to inform HRA practitioners. To this end, the process of estimating HEPs is demonstrated based on feed-and-bleed operations using HRA data from the two systems.

SACADA and HuREX: Part 1. the use of SACADA and HuREX systems to collect human reliability data

  • Chang, Yung Hsien James;Kim, Yochan;Park, Jinkyun;Criscione, Lawrence
    • Nuclear Engineering and Technology
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    • v.54 no.5
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    • pp.1686-1697
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    • 2022
  • As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), the primary role of human reliability analysis (HRA) is to provide credible estimations of the human error probabilities (HEPs) of safety-critical tasks. Accordingly, HRA community has emphasized the accumulation of HRA data to support HRA practitioners for many decades. To this end, it is critical to resolve practical problems including (but not limited to): (1) how to collect HRA data from available information sources, and (2) how to inform HRA practitioners with the collected HRA data. In this regard, the U.S. Nuclear Regulatory Commission (NRC) and Korea Atomic Energy Research Institute (KAERI) independently initiated two large projects to accumulate HRA data by using full-scale simulators (i.e., simulator data). In terms of resolving the first practical problem, the NRC and KAERI developed two dedicated HRA data collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) and HuREX (Human Reliability data EXtraction), respectively. In addition, to inform HRA practitioners, the NRC and KAERI proposed several ideas to extract useful information from simulator data. This paper is the first of two papers to discuss the technical underpinnings of the development of the SACADA and HuREX systems.

Analysis of Application Message Protocol for Control Network in Green Power Systems (차세대 그린 에너지 발전 시설을 위한 응용 메시지 프로토콜의 분석 및 응용)

  • Kwon, Ki-Hyup;Kim, Dong-Sung
    • Journal of Institute of Control, Robotics and Systems
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    • v.15 no.12
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    • pp.1209-1215
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    • 2009
  • This paper discusses a common message protocol for green power systems such as tidal, wind, photovoltaic, and solar systems. For this investigations and analysis, existing protocols such as ELCOM-90, TASE.1, ICCP/TASE.2 and SCADA were analyzed for the application of green power systems in view of real-time property and reliability. For the analysis, the practical example of green power system using SACADA and ICCP are investigated and discussed. As a future direction of this investigations, the feasibility analysis of manufacturing message specification(ISO-9560) for green power system is discussed.