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Lee, Seung Jun
Nuclear Safety Assessment and Plant HMI Evolution Lab.
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dc.citation.endPage 384 -
dc.citation.number 2 -
dc.citation.startPage 375 -
dc.citation.title ANNALS OF NUCLEAR ENERGY -
dc.citation.volume 87 -
dc.contributor.author Lee, Seung Jun -
dc.contributor.author Jung, Wondea -
dc.contributor.author Yang, Joon-Eon -
dc.date.accessioned 2023-12-22T00:12:59Z -
dc.date.available 2023-12-22T00:12:59Z -
dc.date.created 2016-06-07 -
dc.date.issued 2016-01 -
dc.description.abstract Digital systems have unique features that are not applied in analog systems, and these features should be considered in a system safety evaluation, especially in safety critical systems such as nuclear power plants (NPPs). Among the distinguishable features of digital systems, fault-tolerant techniques might be one of the most beneficial features to enhance the system safety. If a fault is detected by the fault-tolerant techniques, then the effect of the fault is isolated from the system output to ensure the system safety. In digital instrumentation and control systems in NPPs such as a reactor protection system and an engineered safety features actuation system, multiple fault-tolerant techniques are designed to prevent the undesired system behaviors by faults. However, the effect of fault-tolerant techniques has not been appropriately reflected in the probabilistic safety assessment (PSA) models for NPPs. In this work, a method to develop a PSA model with consideration of the effect of the fault-tolerant techniques in an NPP digital reactor protection system was proposed. Because multiple fault-tolerant techniques have a different inspection range and inspection time, it was proposed to divide the areas according to the inspecting functions. Each area has the specific failure probability and fault detection coverage. For an application, a digital reactor protection system that aims to automatically generate a trip signal in an emergency situation was evaluated. The failure probability and detection methods of each failure mode were identified based on the failure mode and effect analysis (FMEA) data. From the results, it was observed that fault-tolerant techniques have a significant effect on the system reliability. It is expected that more accurate and reasonable digitalized NPP safety evaluation can be achieved using the proposed method. -
dc.identifier.bibliographicCitation ANNALS OF NUCLEAR ENERGY, v.87, no.2, pp.375 - 384 -
dc.identifier.doi 10.1016/j.anucene.2015.07.039 -
dc.identifier.issn 0306-4549 -
dc.identifier.scopusid 2-s2.0-84943565717 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/19476 -
dc.identifier.url http://www.sciencedirect.com/science/article/pii/S0306454915004053 -
dc.identifier.wosid 000367697800087 -
dc.language 영어 -
dc.publisher PERGAMON-ELSEVIER SCIENCE LTD -
dc.title PSA model with consideration of the effect of fault-tolerant techniques in digital I&C systems -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Digital I & C system -
dc.subject.keywordAuthor Probabilistic safety assessment -
dc.subject.keywordAuthor Fault tree -
dc.subject.keywordAuthor Fault-tolerant technique -
dc.subject.keywordAuthor Fault detection coverage -

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