文献翻译-反应堆压力容器的老化和生命体系

中英文翻译AgingandLifeManagementSystemofReactorPressureVesselYa-JinLiu,JiangGuo,Kai-KaiGuSchoolofPowerandMechanicalEngineering,WuhanUniversity,Wuhan,ChinaE-mail:ReceivedMay16,2011;revisedJune16,2011;July10,2011Abstract:Reactorpressurevessel(RPV),theonlykeycomponentthatcannotbereplacedinnuclearpowerplants(NPPs),isthemainbarrieragainsttheradioactiveleakage.ThelifetimeofNPPsisdependentheavilyonthelifeofRPV,andthus,theagingandliferesearchonaRPVisakeyfactorindeterminingthelifeextensionofNPPs.ThepurposeofthispaperistointroduceanagingandlifemanagementsystemforanoperatingRPVwhichcanbeusedasareferenceofthelifetimeextension.Inordertorealizetheobjective,anagingandlifemanagementsystemwasdeveloped.Itisancomprehensiveknowledgemanagementsystemthatintegratesdecentralizedinformationandservesasavaluabledatacenter.BasedonthestorageandmanagementofRPVstateinformationandoperationdata,thissystemprovidesreal-timemonitoringofimportantoperatingparameters,evaluationofirradiationembrittlement,andRPVagingassessment.Therefore,itisanticipatedthatthedevelopedsystemcanbeusedasanefficienttoolforagingandlifeestimationofRPV.Keywords:ReactorPressureVessel,NuclearPowerPlants,AgingandLifeManagement1.IntroductionAsthemainbarrieragainsttheradioactiveleakage,reactorpressurevessel(RPV)istheuniquecomponentofnuclearpowerplants(NPPs).So,thelifetimeofNPPslargelydependsontheRPV.TheagingandliferesearchonaRPVisakeyfactorindeterminingthelifeextensionofNPPs.DuetotheimportantfunctionofRPVinthesafetyofNPPs,itisessentialtokeepstructureintegralandfunctionperfectundernotonlynormaloperatingconditionsbutalsothetestconditionsoraccidentconditions,andavoidthenon-ductilefractureorradioactiveleakage.TheimplementationofRPVagingevaluationmanagementneedsinformationsuchasrawdataofRPVde-signing,manufacturing,installmentanddebugging,re-al-timeoperationdata,dailymaintenanceinformationandoperationexperiencefeedback.Butalltheinformationisscatteredovermanydifferentdepartments.Asaresult,itisimportantfortheRPVagingandlifemanagementtoobtain,organize,share,updateandinnovatethediscreteinformationwithascientificmethod,andmakeitavailable.Tosolvethisproblem,theagingandlifemanagementsystemofRPVispresented,thefunctionreferencemodelofagingandlifemanagementisdiscussed,thegeneralarchitectureisestablished,andtheprincipleandmethodsofinformationorganizationareparticularlyintroduced.2.ResearchStatusInthedevelopmentofRPVagingmanagementsystem,thecorrespondingregulations,standardandguidearepromulgatedbyIAEA,NRCandASME/ASTM.Theseregulations,standardandguideprovidethestandardsofpropertyparametersofRPVmaterialandthecorrectivemeasureswhennecessary,soastoensurethestructuralintegrityofRPV.Intheagingmanagementresearchandimplementation,muchworkhasbeendoneinUnitedStates,Frenchandothernuclearcountries.Theseworksincludetheagingmechanism,structuralintegrity,onlinemonitoring,in-serviceinspectionandanti-agingmeasures.Meanwhile,theeconomyanalysisworkforthelifemanagementalsobegins.Indatabaseconstruction,basedonthedecadesofoperatingexperience,themajorforeignnuclearcountriespossessrelativelycompletedatabase.Onthebasisofthedatabase,severalagingmanagementsoftwaresystemsaredevelopedwhichmaketheagingmanagementmoreobjectiveandaccurate.DomesticresearchesonRPVagingmanagementarestillattheirearlystage.Theresearchesandpracticesmainlyfocusonthenuclearplant.Theachievementsoftheresearchinform,contentandimplementingeffectsarefarfromperfect.Thereisstillalongwaytogotoformsystematicindustryrulesandregulations.Mean-while,thecriticaltechnologyofinspectionandmonitoringstilldependsonforeignresearchinstitutionsbecauseofthelackofindependentintellectualpropertyrights.Thus,itisessentialtoimproveourscientificresearchstrengthanddeveloptheRPVagingmanagementsystemwithindependentintellectualpropertyrights.AlthoughmanyNPPshavetheirownagingManage-mentdatabases,buttheoperatingexperienceinrecentyearsshowsthat,thelackofrawdata,historicaloperatinginformation,andhistoricalmaintenancedataexertsabadeffectontheRPVagingmanagement,especiallyonthetrendanalysisandpredictionofthecomponentperformanceandremaininglife,andthejudgmentandevaluationofthedegradation,failureandfaultcausedbyagingeffects.Moreover,thereisnoplatformforthein-formationexchangeamongdomesticNPPs.ThecircumstancesarenotconducivetoinformationsharingandthedeepeningdevelopmentoftheRPVagingmanagement.3.ObjectivesandFunctions3.1.ObjectivesInordertoimproveagingandlifemanagementoftheNPPs,weneedtoensurethesecurity,reliabilityandefficiencyoftheplantsbysearchingfortheproblemsbroughtbyacceleratedagingresultingfromdesigndefects,changes,rebuilding,andenvironment,buildingagingassessmentandlifepredictionmodelanddevelopingpracticalmeasuresforimprovement.Andalltheseworksshouldbebasedontheconditionmonitoringinformationandhistoricaldata.IntheearlytimeoftheNPPs,theincompletecollectionofequipmentinformation,thelackofrawdataandtechnologyandtherelativelylowevaluationlevelhavenosignificanteffectsonthedailyproduction.However,theywillcertainlyexertbadeffectsontheevaluationofplantlife,safetymargin,andagingtrend.Therearethreemainaimsofthissystem.Thefirstoneistocollectvariousdata,recordsandinformationneededbytheagingandlifemanagement.Thesecondoneistostoretheelectronicdatainformationbydatabase.Andthelastoneistominethekeyperformanceindexfrommassivehistoricalandreal-timedataanddeterminewhetherspecificvalueswithinthenormalrange.Itishopedthatthedevelopedsystemcanhelpuserstocompletetheprocessofinformationperception,knowledgemodelingandknowledgeanalysis,andtrainnewtechnicalpersonnel.ThedetailsareshownintheTable1.NowadaysbecauseAIcannotyetcompletelyreplacehumankind,thissystemcanbeusedasaneffectivetooltohelpacceleratingandshorteningthethinkingprocess.WiththefurtherunderstandingofRPVagingmechanismandthecontinuousdevelopmentoftheagingandlifeassessmentlevelathomeandabroad,thesysteminformationwillbegraduallyimproved,andtheknowledgewillbefurtherenriched,thusitcanlayasolidfoundationfortheresearchesofRPVagingandlifemanagement.3.2.FunctionsBasedonthecomprehensivestudy,actualdemand,andtherelevantstudiesforreferences,thefunctionsofthesystemareshowninFigure1.Therearesixmoduleswhicharebasicinformationmanagement,in-serviceinspectionmanagement,waterchemistryandoperationmanagement,maintenancemanagement,experiencesfeedback,aginganalysisandassessment.1)BasicInformationManagement.Thismoduleisde-signedtomanagetherawdataofRPVindesigning,manufacturing,installmentanddebuggingin3Dmodel.2)In-serviceInspectionManagement.Thismodulemainlyprovidesin-serviceinspection,includingdefectmanagement,defectanalysis,trendanalysisandinspectionreports.3)WaterChemistryandOperationManagement.Thismoduleisusedtomanagewaterchemistryinformation,operationinformation,transientparameterstatistics,andoverhaulcontrolandanalysis.4)MaintenanceManagement.Thismoduleisusedtorecordthemaintenanceinformationofdefectivedeviceswhichincludesmaintenancetools,maintenanceprocessrecords,workticketstatistics,andtrendanalysis.5)ExperienceFeedbackManagement.Thismoduleprovidestheinterfacetomanageexperiencefeedbackathomeandabroad,andlaythefoundationfortheagingevaluationfollow-up.6)AgingAnalysisandAssessment.Thisisthecorefunctionofthesystem.TheRPVagingconditionisanalyzedbyemployingdifferenttheories,suchasirradiationembrittlementevaluation,wateranalysisandevaluation,calculationofP-Tcurves,PTSeventanalysis,crackevaluation,fatigueevaluationandleakdetection4.TypicalApplications4.1.RPV3DModelBecauseofitscomplexinternalstructureandhighradioactivity,mostofstaffmembersfailtounderstanditsstructureindetail,especiallyitsoperationprinciple.InordertodescribeintegralstructureofRPVexactly,the3DmodelisconstructedbyVRtechnology.Comparingwithtraditional2Dgraphics,3DmodelcandescribetheRPVstructureinamoreintuitiveandvisualmethod,soastoimprovetheintelligibilityofinformation.TheintegralstructureofRPVisshowninFigure2.Throughthisway,userscanfreelyrotateandmovethemodeltogetappropriatedirectionandangleofobservationasiftheymoveitwithintherealenvironment.Inaddition,userscanchoosethespecifiedpartofRPVforobservation.ThevisualizationofthetopofRPVispresentedinFigure3.4.2.In-ServiceInspectionManagementIn-serviceinspectionisofgreatestimportanceforNPPs.Inthismodule,alargeamountofinformationaboutequipmentperformanceisrecorded,whichisimportantfortheagingevaluationofRPV.Thereareseveralinspectionmethods,suchaseddycurrenttesting(ET),ultrasonictesting(UT),penetranttesting(PT),andradiographictesting(RT).Whenweusedifferentinspectionmethods,wewillrecorddifferentcontentsaccordingly.Thus,coreworkofthissystemistofindareasonablemethodtoorganizethisinformation.Basedonthecomprehensiveinvestigationandanalysis,thissystemadoptsopensystemarchitectureandhierarchicaldesigningmethodsoastoorganizeandmanagethecontentsofdifferentinspectionmethods,thusmakingthemanagementanddisplaymodeautomaticallyconsistentwiththeinspectionmethods.PartialinspectionresultsofboltsofthetopofRPVarepresentedinFigure4.TheboltsareinspectedthroughET.4.3.IrradiationEmbrittlementEvaluationIrradiationembrittlementevaluationofRPViskeytotheaginganalysisandassessment.Itsaccuracyandintegralitydirectlydeterminesthesafety,reliabilityandeconomyofNPPs.Theagingconditioncanbeevaluatedonthebasisofthein-serviceinspectioninformation,historicaloperationdata,maintenanceinformationandexperiencefeedback.Basemetalandweldarethemainlyobjectsoftheirradiationembrittlementevaluation.ThemainassessmentindexincludesUSE,PTS,ART,etc.Figure5showsthetrendofUSEofbasemetalandweld.Theblacklineisforpredictivevalue,theredlineisfordesignvalue,andthegreenlineisforvalueattheendoflifetime.UserscangettheaccuratevalueofUSEwhentheymovetheirmouseoverthecurves.Inaddition,therearevarioussortsofinformationaboutirradiationembrittlementevaluationwhichareshowninFigure6,suchasirradiationmonitoringdata,basicinformationofmaterial,installpositionofirradiationmonitoringtube,andextractionschemeofirradiationmonitoringtube.Comparativeanalysisoftheinformationabovecanimprovetheveracityofevaluationresults.5.ConclusionsInthispaper,asystemaimedatagingandlifeevaluationofRPVisproposed.Basedonthecomprehensiveinvestigationandanalysis,thearchitectureofthesystemisdesignedanditsfunctionsaredeveloped.Thissystemhasexcellentcapability,openingandexpansibility.1)Itrealizesthestandardizedmanagementofaginginformationandthecentralizedmanagementofthediscretedata,whichcanbeusedintheevaluationafter-wards.2)Therationalutilizationofinformationisrealizedbyusinginformationtechnology,virtualrealitytechnologyandmulti-agenttechnology,anditimprovestheutilizationandunderstandabilityofinformation.3)Thespecialmoduleforagingevaluationisdevel-oped.ItevaluatestheRPVagingconditionfromdifferentaspects,andlaysfoundationfortheintegralevaluation.ThissystemisnowinuseinaNPPinChinaandprovestobeanexcellentsystem.Itcaneffectivelysolveproblemsofagingmanagement.However,theagingmanagementinChinaisstillatitsinitialstage,andmuchworkneedstobedone.6.References1D.-P.Kong,H.LiandH.-L.Zheng,“LifeManagementofReactorPressureVesselatQinshanNuclearPowerPlant,”NuclearPowerEngineering,inChinese,Vol.29,No.6,2008,pp.110-114.2J.C.Kim,J.B.Choi,Y.S.Chang,Y.J.KimandY.W.Park,“DevelopmentofWeb-BasedFatigueLifeEvaluationSystemforReactorPressureVessel,”SafetyandStructuralIntegrity,Vol.120,No.25,2007,pp.25-30.3K.Anandakumaran,“AgingandConditionMonitoringStudiesofCompositeInsulationCablesUsedinNuclearPowerPlants,”DielectricsandElectricalInsulation,IEEETransactionson,Vol.14,No.1,2007,pp.227-237.4Z.F.Tong,H.LinandG.-S.Ning,“PredictionModelonIrradiationEmbrittlementofLowCopperAlloyReactorPressureVesselSteels,”AtomicEnergyScienceandTechnology,inChinese,Vol.43,2009,pp.103-108.5K.OnizawaandH.Matsuzawa,“StudyonFactorsImportanttoStructuralIntegrityofReactorPressureVesselduringPTSwithRegardtoFractureProbability,”ASMEPressureVesselsandPipingConference,Vol.1,2010,pp.411-418.6M.Brumovsky,“WaysforExtendingtheReactorPres-sureVesselLifetime,”ProceedingsoftheASMEPres-sureVesselsandPipingConference,Vol.7,2009,pp.129-135.7G.Bezdikian,“NuclearPWRPlantsLifeManagementReactorPressureVesselStrategicEvaluationforFluenceinRelationwithIntegrityAssessment,”ProceedingsoftheASMEPressureVesselsandPipingConference,Vol.7,2009,pp.579-587.8W.F.Wu,C.S.ShinandC.H.Tsai,“AReliabilityAssessmentofReactorPressureVessels,”InternationalJournalofPressureVesselsandPiping,Vol.57,No.1,1994,pp.77-84.9V.N.ShahandW.L.Server,“AnagingManagementApproachforPressurizedWaterReactorPressureVessels,”InternationalJournalofPressureVesselsandPiping,Vol.54,No.1-2,1993,pp.317-340.10M.A.Rinckel,“ReactorPressureVesselIntegrityPro-gram,”NuclearEngineeringandDesign,Vol.181,No.1-3,1998,pp.17-39.11G.E.Lucas.“AnEvolutionofUnderstandingofReactorPressureVesselSteelEmbrittlement,”JournalofNuclearMaterials,Vol.407,No.1,2010,pp.59-69.12S.Leclercq,D.Lidbury,S.V.Dyck,etal.,“Perform60PredictionoftheEffectsofRadiationforReactorPressureVesselandin-CoreMaterialsUsingMulti-ScaleModeling60YearsForeseenPlantLifetime,”JournalofNuclearMaterials,Vol.406,No.1,2010,pp.193-203.13J.M.Hyde,M.G.Burke,B.Gault,etal.,“AtomProbeTomographyofReactorPressureVesselSteels:AnAnalysisofDataIntegrity,”Ultramicroscopy,Vol.111,No.6,2011,pp.676-682.14J.Y.Huang,J.J.Yeh,R.C.Kuo,etal.,“FatigueCrackGrowthBehaviorofReactorPressureVesselSteelsinAirandHigh-TemperatureWaterEnvironments,”InternationalJournalofPressureVesselsandPiping,Vol.85,No.11,2008,pp.772-781.15F.J.Blom,“ReactorPressureVesselEmbrittlementofNPPBorssele:DesignLifetimeandLifetimeExtension,”NuclearEngineeringandDesign,Vol.237,No.20-21,2007,pp.2098-2104.16U.B.Baek,K.S.Ryu,A.Kim,etal.,“AgingEstimationofReactorPressureVesselintheFieldUsingMagneticProperties,”JournalofLossPreventionintheProcessIndustries,Vol.22,No.6,2009,pp.971-974.17A.AlMazouzi,A.Alamo,D.Lidbury,etal.,“Perform60:PredictionoftheEffectsofRadiationforReactorPressureVesselandin-CoreMaterialsUsingMulti-ScaleModelling60YearsForeseenPlantLifetime,”NuclearEngineeringandDesign,inPress,CorrectedProof.18G.Bezdikian,“NuclearPWRPlantsLifeManagementReactorPressureVesselStrategicEvaluationforFluenceinRelationwithIntegrityAssessment,”AmericanSocietyofMechanicalEngineers,NewYork,2009.19P.Pareige,P.AugerandJ.C.VanDuysen,“EffectsofNeutronRadiationontheAgingofNuclearReactorPressureVesselSteelObservationattheAtomicLevelUsinganAtomicProbe,”JournalDePhysiqueIv,Vol.11,No.1,2001,pp.39-48.20D.P.G.Lidbury,A.H.Sherry,B.R.Bass,etal.,“Vali-dationofConstraint-BasedMethodologyinStructuralIntegrityofFerriticSteelsforNuclearReactorPressureVessels,”Fatigue&FractureofEngineeringMaterials&Structures,Vol.29,No.9-10,2006,pp.829-849.21C.A.EnglishandJ.M.Hyde,“RadiationEmbrittlementofReactorPressureVesselSteels,”In:I.Milne,R.O.RitchieandB.Karihaloo,ComprehensiveStructuralIn-tegrity,Pergamon,Oxford,2003,pp.351-398.中文译文反应堆压力容器的老化和生命体系刘亚津，郭江，顾凯凯中国，武汉，武汉大学，能源与材料工程学院2011.5.26验收，2011.6.16-2011.7.10审核摘要：反应堆压力容器（反应堆压力容器），核电厂（核电站）唯一的不可替代的关键组成部分，是防止放射性泄漏的主要障碍。核电厂的使用寿命在很大程度上依赖于反应堆压力容器的寿命，因此，核电站反应堆压力容器的老化和寿命的研究是决定核电厂寿命延长的一个关键因素。本文的目的是引入一种可操作的反应堆压力容器老化和寿命管理系统，它可以用来作为寿命延长的参照。为了实现这个目标，开发了一种老化和寿命管理系统。这是一个全面的知识管理系统，它整合分散的信息，而且作为一个珍贵的数据中心。基于反应堆压力容器状态信息和操作数据的存储和管理，该系统提供了实时的重要操作参数的监控，辐照脆化的评价，反应堆压力容器老化评价。因此，可以预测所研发的系统可以用来作为反应堆压力容器老化和寿命评估的一个有效的工具。关键字：反应堆压力容器，核电厂，老化和寿命管理1.介绍反应堆压力容器（反应堆压力容器）是核电厂（NPPs）的独特组成部分，它作为防止放射性泄露的主要障碍。因此，核电厂的使用寿命在很大程度上取决于反应堆压力容器。反应堆压力容器上的老化和寿命的研究是决定核电站寿命延长的关键因素。由于反应堆压力容器在核电厂的安全性方面的重要功能，不仅在正常工作条件下而且在试验条件或危险工况下，保证反应堆压力容器结构完整和功能完美是必要的，并避免非延性断裂或放射性泄漏。反应堆压力容器老化评价管理的实施需要原始数据信息，像反应堆压力容器设计，制造，安装和调试，实时的操作数据，日常维护信息和运行经验反馈等。但是，所有的信息被分散在众多不同的部分。结果，用一种科学的方法获取，组织，分享，更新和创新的分散的信息对于反应堆压力容器老化和寿命管理系统是很重要的，并是之可行。为了解决这个问题，提出了反应堆压力容器老化和寿命管理系统，并讨论了参考模型老化和寿命管理的功能，建立的一般的结构，特别介绍了信息组织的原则和方法。2.研究现状随着反应堆压力容器老化管理系统的发展，IAEA，NRC和ASME/ASTM颁布相应的法规，标准和指导文件。这些法规，标准和指导文件提供了反应堆压力容器材料和必要时的纠正措施的合适的参数，这样才能保证反应堆压力容器的结构完整性。在老化管理的研究和实施方面，美国，法国和其他核国家已经做了很多。这些工作包括了老化机制，结构完整性，在线监测，在役检查和抗衰老措施。同时，寿命管理的经济性分析工作也开始了。在数据库建设中，在几十年的操作经验的基础上，主要的国外核国家拥有相对完整的数据库。在数据库的基础上，一些老化管理软件系统的开发，使得老化管理更加客观和准确。反应堆压力容器老化管理系统的国内研究仍处于早期阶段。这些研究和实践主要集中在核电厂上面。这些研究成果的形式，内容和实施效果还不尽完美。形成系统的行业规则和法规还有一段很长的路要走。同时，检查和监测的关键技术仍然依赖于国外研究机构，因为缺乏自主知识产权。因此，提高我们的科研实力和开发具有自主知识产权的反应堆压力容器老化管理系统是很必要的。尽管很多核电厂都有他们自己的老化管理数据库，但是近几年的操作经验表明，老化效应导致原始数据，历史操作信息和历史维护数据的缺乏，这对反应堆压力容器老化管理产生了很坏的影响，尤其是在组成元件表现和保持寿命的趋势分析和预测方面，还有判断和评价的退化，失败和错误等。此外，也不存在国内核电厂数据交流的平台。这种环境是不利于信息共享和反应堆压力容器老化管理的深入发展的。3.目标和功能3.1.目标为了提高核电厂的老化和寿命管理，我们需要保证反应堆的安全，可靠性和效率，通过查找由加速老化导致的设计缺陷，改变，重建和环境的问题，来建设老化评价和寿命预测模型和发展实际的提高措施。而且所有这些工作都应以状态监测的信息和历史数据为基础。在核电站早期的时候，设备信息收集不完整，原始数据和技术的缺乏和相对低的评价水平对于日常生产没有明显的效果。然而，他们肯定会对反应堆的寿命，安全余地及老化趋势的评估产生不良影响。这个系统有三个主要的目的。第一个目的是收集老化和寿命管理所需要的各种不同数据，记录和信息。第二个目的是通过数据库存储电子数据信息。最后一个目的是从大量的历史和实时数据开采重要的性能指数，并确定具体的值是否在正常范围内。希望所开发的这系统可以帮助用户完成信息感知，知识建模和知识分析，培训新的技术人员等的过程。详见下表1。表1.系统的目的阶段目的信息感知从多种多样的资源数据中获得有用信息，然后总结和整合数据用来挖掘多种多样的资源和多维的数据中的重要工作指数知识建模挖掘多种多样的资源和多维的数据中的重要工作指数知识分析评价反应堆压力容器的老化状况，预测他的老化程度并陈述减缓老化的措施知识陈述用虚拟真实的技术来提高信息的可理解性如今因为AI不能完全取代人类，该系统可作为一个有效的工具来帮助加速和缩短思维过程。随着对反应堆压力容器老化机制的深入理解和国内外老化和寿命评价水平的不断发展，系统的信息将会逐步完善，而且知识将进一步丰富，因此这为反应堆压力容器老化和寿命管理奠定了坚实的基础。3.2.功能基于全面的研究，实际的要求和相关的研究作为参考，系统的功能如图1所示.图1.反应堆压力容器的老化和寿命管理系统的功能3D建模管理安装数据管理制造数据管理基本信息管理设计数据管理检查报告管理特殊工具管理在役检查项目在役检查管理在役检查数据检修控制与分析瞬时参数统计操作信息水化学和操作管理水化学信息管理工作票统计和分析维修过程记录维修管理维修工具管理经验反馈咨询反应堆压力容器的老化和寿命管理系统经验反馈经验反馈统计经验反馈管理泄露检测疲劳评价裂纹评价PTS事件分析P-T曲线计算水质分析和评价老化分析和评价辐照脆化评价有六个单元，他们是基本信息管理，在役检查管理，水化学和操作管理，维护管理，经验反馈，老化分析和评估。1）基本信息管理。此单元是设计来管理反应堆压力容器的设计，制造，安装和调试的三维模型管理的原始数据。2）在役检查管理。该单元主要提供在役检查，包括缺陷管理，缺陷分析，趋势分析和检查报告。3）水化学和操作管理。此单元用于管理水化学信息，操作信息，瞬时参数统计和检修控制与分析。4）维修管理。这个单元是用来记录有缺陷的设备的维修信息，该维护信息包括维修工具，维修过程记录，工作票统计和趋势分析。5）经验反馈管理。该单元提供的接口来管理在国内外管理经验的反馈，并为接下来的老化评价奠定了基础。6）老化分析和评价。这是该系统的核心功能。反应堆压力容器老化条件分析采用不同的理论，如辐照脆化评价，水质分析和评价，P-T曲线计算，PTS事件分析，裂纹评价，疲劳评价和泄漏检测。4.典型应用4.1.反应堆压力容器3D模型由于其复杂的内部结构和强放射性，大部分工作人员没有详细理解它的结构，特别是它的工作原理。为了精确地描述反应堆压力容器的整体结构，通过VR技术建立了3D模型。相对于传统的2D图形，3D模型可以以一种更加直观的和视觉的方法描述反应堆压力容器的结构，以此提高信息的可懂度。反应堆压力容器的积分结构如图2所示。通过这种方式，用户可以自由地旋转和移动模型得到适当的方向和角度观测，就像他们可以在真实环境内移动它。另外，用户可以选择反应堆压力容器的特定部分来观察。反应堆压力容器的顶部的可视图如图3所示。4.2.在役检测管理在役检测是核电厂最重要的部分。在此单元中，记录了关于设备表现的大量的信息，这对反应堆压力容器的老化评价是很重要的。检查方法有几种，如涡流检测（ET），超声波探伤（UT），渗透探伤（PT）和射线探伤（RT）。当我们使用不同的检测方法，我们会相应的记录不同的内容。因此，这个系统的核心任务是找到一个合理