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30万千瓦核电站压水堆压力容器的应力分析和试验.docx

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30万千瓦核电站压水堆压力容器的应力分析和试验 Introduction Themainpurposeofthispaperistoprovideananalysisofthestressandstraininthepressurevesselofa300,000-kilowattnuclearpowerplantpressurizedwaterreactor,aswellasitstesting.Thepressurevesselisanintegralcomponentofthenuclearpowerplantandisresponsibleforcontainingthenuclearfuel,aswellasthecoolant,pressureandstructuralloads. Background Thereactorpressurevessel(RPV)ofthepressurizedwaterreactorisoneofthemostcriticalcomponentsofthenuclearpowerplant.AstheRPVcontainsthereactorcoreandcoolant,itisessentialthatitisconstructedfrommaterialsofhighstrength,whileconcurrentlyhavingtheabilitytotoleratethefluctuatingthermalandpressureloadsinthereactor.TheRPVisspecificallydesignedtobeusedfordecadeswithoutdeterioratingorlosingitsstructuralintegrity. StressAnalysis Thestressanalysisofapressurevesselisessentialtoensurethatitcanwithstandthevariousthermal,pressure,andstructuralloads.Thestressanalysisistypicallyperformedusingfiniteelementmethods,whichworkbybreakingtheobjectbeinganalyzeddownintoaseriesoffiniteelements.Thefiniteelementsarethenmodeledtomatchthematerialpropertiesandgeometricalshapeoftheoriginalobject,andthestructureisanalyzedforstressandstrain. ThemostimportantareasoftheRPVthatareanalyzedforstressarethehead,cylindricalshell,andbottomregion.Theseareascanundergosignificantlevelsofstressduringoperationduetothevariousthermalandpressureloads.ThefirststepinthisstressanalysisistoidentifytheloadingconditionsthattheRPVwillexperienceduringitsoperation,includinginternalpressure,temperature,radiation,andcoolantflow.Theseconditionsarethenanalyzedtodeterminethemaximumexpectedstressinthepressurizedvessel. TrialTesting Trialtestingandprototypeverificationisanessentialphaseinthedevelopmentofnewpressurizedwaterreactordesigns.VarioustestsareconductedtoevaluatetheperformanceandsafetyoftheRPV.Thesetestsincludehydroproofpressuretests,bursttests,thermalstresstests,andfatiguetests. HydraulicpressuretestsareconductedtoverifythestructuralintegrityoftheRPVathigh-pressureconditi