Nuclear Engineering and Technology

  • 제41권6호
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  • Pages.849-858
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  • 2009
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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AN OVERVIEW OF RISK QUANTIFICATION ISSUES FOR DIGITALIZED NUCLEAR POWER PLANTS USING A STATIC FAULT TREE

  • 발행 : 2009.08.31
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초록

Risk caused by safety-critical instrumentation and control (I&C) systems considerably affects overall plant risk. As digitalization of safety-critical systems in nuclear power plants progresses, a risk model of a digitalized safety system is required and must be included in a plant safety model in order to assess this risk effect on the plant. Unique features of a digital system cause some challenges in risk modeling. This article aims at providing an overview of the issues related to the development of a static fault-tree-based risk model. We categorize the complicated issues of digital system probabilistic risk assessment (PRA) into four groups based on their characteristics: hardware module issues, software issues, system issues, and safety function issues. Quantification of the effect of these issues dominates the quality of a developed risk model. Recent research activities for addressing various issues, such as the modeling framework of a software-based system, the software failure probability and the fault coverage of a self monitoring mechanism, are discussed. Although these issues are interrelated and affect each other, the categorized and systematic approach suggested here will provide a proper insight for analyzing risk from a digital system.

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피인용 문헌

  1. The Software Reliability Evaluation of a Nuclear Controller Software Using a Fault Detection Coverage Based on the Fault Weight vol.5, pp.9, 2016, https://doi.org/10.3745/KTCCS.2016.5.9.275
  2. A novel framework for the reliability modelling of repairable multistate complex mechanical systems considering propagation relationships pp.07488017, 2018, https://doi.org/10.1002/qre.2382