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dc.contributor.authorBui, Ha
dc.contributor.authorSakurahara, Tatsuya
dc.contributor.authorReihani, Seyed
dc.contributor.authorKee, Ernie
dc.contributor.authorMohaghegh, Zahra
dc.date.accessioned2024-12-24T19:18:01Z
dc.date.available2024-12-24T19:18:01Z
dc.date.copyright1/12/2024 12:00:00 AM
dc.date.issued2024
dc.identifier.issn2332-9017
dc.identifier.otherrisk_010_02_021202.pdf
dc.identifier.urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4303689
dc.description.abstractRecently, there has been an increasing use of advanced modeling and simulation in the nuclear domain across academia, industry, and regulatory agencies to improve the realism in capturing complex and highly spatiotemporal phenomena within the probabilistic risk assessment (PRA) of existing nuclear power plants (NPPs). Advanced modeling and simulation have also been used to accelerate the risk-informed design, licensing, and operationalization of advanced nuclear reactors. Validation of simulation models traditionally relies on empirical validation approaches which require enough validation data. Such validation data are, however, usually costly to obtain in the contexts of the nuclear industry. To overcome this challenge and to effectively support the use of simulation models in PRA and risk-informed decision-making applications, a systematic and scientifically justifiable validation methodology, namely, the probabilistic validation (PV) methodology, has been developed. This methodology leverages uncertainty analysis to support the validity assessment of the simulation prediction. The theoretical foundation and methodological platform of the PV methodology have been reported in the first paper of this two-part series. The purpose of this second paper is to computationalize the PV methodology, embedded in an integrated PRA framework, and apply it for a hierarchical fire simulation model used in NPP Fire PRA.
dc.publisherThe American Society of Mechanical Engineers (ASME)
dc.titleProbabilistic Validation: Computational Platform and Application to Fire Probabilistic Risk Assessment of Nuclear Power Plants
dc.typeJournal Paper
dc.journal.volume10
dc.journal.issue2
dc.journal.titleASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg
dc.identifier.doi10.1115/1.4063071
dc.journal.fristpage21202-1
dc.journal.lastpage21202-23
dc.page23
dc.treeASCE-ASME J Risk and Uncert in Engrg Sys Part B Mech Engrg:;2024:;volume( 010 ):;issue: 002
dc.contenttypeFulltext


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