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1、ProgressinNuclearEnergy53(2011)1e9ContentslistsavailableatScienceDirectProgressinNuclearEnergyjournalhomepage:www.elsevier.com/locate/pnuceneDevelopmentofTSAC1.0andapplicationtoreactivityinsertionaccidentofCARRRonghuaChen,G.H.Su,WenxiTian,SuizhengQiu,DounanJiaSchoolof
2、NuclearScienceandTechnology,StateKeyLaboratoryofMultiphaseFlowinPowerEngineering,Xi’anJiaotongUniversity,Xi’an710049,ChinaarticleinfoabstractArticlehistory:Inthisstudy,wehavedevelopedathermo-hydraulicandsafetyanalysiscodenamedTSAC1.0withVisualReceived4June2010Fortran6
3、.5toanalyzethethermal-hydrauliccharacteristicsoftheChinaadvancedresearchreactorReceivedinrevisedform(CARR)underreactivityinsertionaccident(RIA)whichwasinducedbyunexpectedcontrolrodwith-29September2010drawalinfullpowercondition.Theneutronkineticmodeldependedonthepointk
4、ineticswithsixAccepted29September2010groupsofdelayedneutronsincludingreactivityfeedbackeffectsanditwasadoptedforthesolutionofreactorpower.Furthermore,anewsimpleandconvenientmodelwasadoptedforthesolutionofthetransientbehaviorsofmainpumpinsteadofthecomplicatedfour-quadr
5、antmodel.Visualinput,real-Keywords:timeprocessinganddynamicvisualizationoutputwereachievedusingMicrosoftVisualStudio.NET2003ChinaadvancedresearchreactorReactivityinsertionaccidenttomaketheapplicationofTSAC1.0muchmoreconvenientintheengineering.ThesimulatedresultsofAcci
6、dentanalysisTSAC1.0werefoundtobeinreasonableagreementwiththoseofRELAP5/MOD3andshowedthattheVisualinterfaceparameters,includingthepeakcoolanttemperature,thepeakheatstructuretemperature,andMDNBR,wereintheacceptablerangeofdesignsafetylimitunderRIA.Ó2010ElsevierLtd.Allrig
7、htsreserved.1.IntroductionAsoneofthemostimportantissuesrelatedtonuclearreactorsafety,thereactivityinsertionaccident(RIA)canresultinanTheCARRisalowpowerandmulti-purposeresearchreactorunwantedincreaseinfissionrate,reactorpowerandtemperature.locatedinBeijing,China.CARRfirs
8、treachedcriticalityonMay13,Theimmediateconsequenceofpowerexcursionisthedamageto2010.Itadoptstank-in-pooltypestructure,lightw