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
Link To Document :
بازگشت