Title of article
Consequencesofmaterialeffectsonin-vesselretentionOriginalResearchArticle
Author/Authors
JeanMarieSeiler، نويسنده , , BrunoTourniaire، نويسنده , , FrançoiseDefoort، نويسنده , , KarineFroment، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2007
Pages
7
From page
1752
To page
1758
Abstract
In-vesselretention(IVR)consistsincoolingthecoriumcontainedinthereactorvesselbynaturalconvectionandreactorcavityflooding.Thisstrategyofsevereaccidentmanagementenablesthecoriumtobekeptinsidethesecondconfinementbarrier:thereactorvessel.ThegeneralapproachwhichisusedtostudyIVRproblemsisa“bounding”approachwhichconsistsinassumingaspecifiedcoriumstratificationinthevesselandthendemonstratingthatthevesselcancopewiththeresultingthermalandmechanicalloads.Thermalloadingonthevesseliscontrolledbytheconvectiveheattransferinsidethemoltencoriuminthelowerhead.Ifthereisnowaterinthevesselandifthecoriumpoolisoverlaidbyaliquidsteellayer,thentheheatfluxmightfocusonthevesselinfrontofthesteellayer(“focusingeffect”)andexceedthedry-outheatflux(CHForDHF).Oneofthecriticalpointsofthesestudiesislinkedtothedeterminationoftheheightofthemoltensteellayerthatcanstratifyabovetheoxidicpool.TheMASCAexperimentshavehighlightedthatpartofmoltensteelmaystratifyundertheoxidiccoriumwhichreducesthethicknessofthesteellayerontopofthepool.Thisbehaviorcanbeexplainedbychemicalinteractionbetweentheoxideandmetallicphasesofthepoolwhichconfirmsthatthesematerialscannotbetreatedasinertspecies.Followingtheseconclusions,amethodologywhichcouplesphysicochemicaleffectsandthermalhydraulicshasbeendevelopedtoaddresstheIVRissue.Themainpurposeofthispaperistopresentthismethodologyanditsapplicationforgivencoriummassinventories.AttentionfocusesontheinfluenceofparameterssuchastheratioU/Zrandoxidationratioofzirconia.Fora1000MWPWR,approximately10tofsteelstratifyatthebottomofthevesselfor40%Zroxidation,and25tfor30%Zroxidation.Thisleadstoa25–50%increaseofthemassofmoltensteelthatisrequiredforavoidingvesselmelt-through.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2007
Journal title
Nuclear Engineering and Design Eslah
Record number
941357
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