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
Link To Document :
https://search.isc.ac/dl/search/defaultta.aspx?DTC=10&DC=894877
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