Design evaluation of emergency core cooling systems using Axiomatic Design

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dc.contributor.authorHeo G.ko
dc.contributor.authorLee S.K.ko
dc.date.accessioned2013-03-06T16:40:00Z-
dc.date.available2013-03-06T16:40:00Z-
dc.date.created2012-02-06-
dc.date.created2012-02-06-
dc.date.issued2007-
dc.identifier.citationNUCLEAR ENGINEERING AND DESIGN, v.237, no.1, pp.38 - 46-
dc.identifier.issn0029-5493-
dc.identifier.urihttp://hdl.handle.net/10203/87629-
dc.description.abstractIn designing nuclear power plants (NPPs), the evaluation of safety is one of the important issues. As a measure for evaluating safety, this paper proposes a methodology to examine the design process of emergency core cooling systems (ECCSs) in NPPs using Axiomatic Design (AD). This is particularly important for identifying vulnerabilities and creating solutions. Korean Advanced Power Reactor 1400 MWe (APR1400) adopted the ECCS, which was improved to meet the stronger safety regulations than that of the current Optimized Power Reactor 1000 MWe (OPR1000). To improve the performance and safety of the ECCS, the various design strategies such as independency or redundancy were implemented, and their effectiveness was confirmed by calculating core damage frequency. We suggest an alternative viewpoint of evaluating the deployment of design strategies in terms of AD methodology. AD suggests two design principles and the visualization tools for organizing design process. The important benefit of AD is that it is capable of providing suitable priorities for deploying design strategies. The reverse engineering driven by AD has been able to show that the design process of the ECCS of APR1400 was improved in comparison to that of OPR1000 from the viewpoint of the coordination of design strategies. (c) 2006 Elsevier B.V. All rights reserved.-
dc.languageEnglish-
dc.publisherELSEVIER SCIENCE SA-
dc.titleDesign evaluation of emergency core cooling systems using Axiomatic Design-
dc.typeArticle-
dc.identifier.wosid000243671000004-
dc.identifier.scopusid2-s2.0-33845391898-
dc.type.rimsART-
dc.citation.volume237-
dc.citation.issue1-
dc.citation.beginningpage38-
dc.citation.endingpage46-
dc.citation.publicationnameNUCLEAR ENGINEERING AND DESIGN-
dc.identifier.doi10.1016/j.nucengdes.2006.06.001-
dc.contributor.localauthorLee S.K.-
dc.contributor.nonIdAuthorHeo G.-
dc.type.journalArticleArticle-
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