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contributor authorPetkov, Gueorgui I.
contributor authorVela-Garcia, Monica
date accessioned2019-02-28T11:05:38Z
date available2019-02-28T11:05:38Z
date copyright3/5/2018 12:00:00 AM
date issued2018
identifier issn2332-8983
identifier otherners_004_02_020913.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252597
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.
publisherThe American Society of Mechanical Engineers (ASME)
titleSevere Accident Context Quantification for Long-Term Station Blackout in Boiling Water Reactor Nuclear Power Plants
typeJournal Paper
journal volume4
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4038928
journal fristpage20913
journal lastpage020913-4
treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
contenttypeFulltext


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