Title of article
AnalysisoftheIAEAresearchreactorbenchmarkproblembytheRETRAC-PCcodeOriginalResearchArticle
Author/Authors
AnisBousbia-Salah، نويسنده , , TewfikHamidouche، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2005
Pages
14
From page
661
To page
674
Abstract
Abasicapproachtoperformsafetyanalysisofanuclearresearchreactorconsistsinusingdeterministicmethodstoverifythattheestablishedacceptancecriteriarelatedtofuelintegrityarefulfilledduringallthestagesofthefacilitylifetime.Thesemethodsshouldbevalidatedagainstalargesetofexperimentalandpostulatedtransients.Sincemeasureddataarenoteasilyavailableintheliterature,theIAEAdefinedtypicaltransientsinageneric10-MWMTRnuclearreactorcoreasabenchmarktestforcomputationaltoolsverification.Inthisframework,anassessmentstudyofthecoupledkinetic–thermal–hydraulicRETRAC-PCcodeispresentedherein.Theconsideredcasesincludetheanalysisofcoredynamicunderramppositivereactivityinsertion,andlossofflowtransients.Ingeneral,theobtainedresultsaresatisfactoryandagreewithresultsobtainedbyothersimilarcodes.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2005
Journal title
Nuclear Engineering and Design Eslah
Record number
894877
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