Title of article
SIMMERmodelofalow-enricheduraniumnon-powerreactorOriginalResearchArticle
Author/Authors
DirkWilhelm، نويسنده , , GuillaumeBiaut، نويسنده , , YoshiharuTobita، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
8
From page
41
To page
48
Abstract
IRSNhasstartedusingthecoupledneutronics–fluiddynamicscodeSIMMER[]tostudycore-disruptiveaccidentsinducedbyinsertionsoflargereactivitiestoproduceveryshortperiodpowerexcursionsinfuelplate-typeandwater-moderatedexperimentalresearchreactors.Untilnow,Frenchsafetyanalysesretainaboundingthermalenergyreleasedandmechanicalyields,deducedfromanalysisofdestructivein-piletestprograms,tostudythebehaviorofsuchreactorsanddesigntheirstructuresandcontainment.
Contrarytothisapproach,thepresentresearchprogramaimsatmodelingthedesignbasisaccidentofresearchreactorswithalow-enrichedfuelusingaCFDcode.Theobjectiveistoanalyzetheeffectsofreactivityfeedbacksandhowtheywouldlimitthegeneratedthermalenergyreleasedinthefuel.Theseaspectsrequireaclosecouplingoftheneutronicstothefluiddynamicsanalysis.Theconsequencesofthenuclearpowerexcursion,thechangesofstateofthefuelandthecoolant,andultimatelythemechanicalenergyreleasedarecalculatedbySIMMER.Forlargestep-wisereactivityintroductions,theDopplereffectand,atalowerextent,thefuelelementthermaldilatation,whichgenerateslocallyadecreaseofthemoderatortofuelratio,limitthepowerexcursionbeforetheenergyreleasedishighenoughtomeltalargepartofthefuel.Moreover,ithasbeenshownthatimposinganexternalreactivityasastep-wiseortime-dependentreactivityintroductionyieldsresultsquitedifferentfromthoseofthephysicalmovementofcontrolrods.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
894977
Link To Document