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dc.contributor.authorPetkov, Gueorgui I.
dc.contributor.authorVela-Garcia, Monica
dc.date.accessioned2019-02-28T11:05:38Z
dc.date.available2019-02-28T11:05:38Z
dc.date.copyright3/5/2018 12:00:00 AM
dc.date.issued2018
dc.identifier.issn2332-8983
dc.identifier.otherners_004_02_020913.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252597
dc.description.abstractThe realistic study of dynamic accident context is an invaluable tool to address the uncertainties and their impact on safety assessment and management. The capacities of the performance evaluation of teamwork (PET) procedure for dynamic context quantification and determination of alternatives, coordination, and monitoring of human performance and decision-making are discussed in this paper. The procedure is based on a thorough description of symptoms during the accident scenario progressions with the use of thermo-hydraulic (TH) model and severe accident (SA) codes (melcor and maap). The opportunities of PET procedure for context quantification are exemplified for the long-term station blackout (LT SBO) accident scenario at Fukushima Daiichi #1 and a hypothetic unmitigated LT SBO at peach bottom #1 boiling water reactor (BWR) reactor nuclear power plants (NPPs). The context quantification of these LT SBO scenarios is based on the IAEA Fukushima Daiichi accident report, “State-of-the-Art Reactor Consequence Analysis” and TH calculations made by using maap code at the EC Joint Research Centre.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleSevere Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
dc.typeJournal Paper
dc.journal.volume4
dc.journal.issue2
dc.journal.titleJournal of Nuclear Engineering and Radiation Science
dc.identifier.doi10.1115/1.4038928
dc.journal.fristpage20913
dc.journal.lastpage020913-4
dc.treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
dc.contenttypeFulltext


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