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 :
بازگشت