严重事故下安全壳内氢气浓度场分布影响因素的初步研究

NuclearPowerEngineering28120072Vol.28.No.1Feb.20070258-0928(2007)01-0099-06100084FLUENTGASFLOWFLUENTRNGk-FLUENTk-GASFLOWk-GASFLOWTL364.4A1[1]FLUENTGASFLOW2.122.1FLUENTFLUENT[2],-FLUENTFLUENTk-k-RNGk-QUICK2.2GASFLOWGASFLOW[34]-GASFLOWGASFLOW23GASFLOW2.1k-2005-05-312006-01-20Vol.28.No.1.200710033.165m20m(1)33174634m350648m3FLUENT4248790.17m3GASFLOW319682.3m31Fig.1GeometricalModelofContainmentofDayaBayNPP3.2LOCA0.3m0.3MPa450K50%0.2kg/s1000s2kg/s10%90%100%0.5kg/s4P1P2P3P4P55(2)FLUENTGASFLOW25Fig.2FivePointsforRecordingLocalFlowParameters4.13P1ε-kRNGε-kω-k3RNGε-kP1ω-kRNGε-k3P1Fig.3HydrogenConcentrationatP1byDifferentTurbulenceModels101ε-k4RNGε-k1(10.3MPa450K50%0.2kg/s)P1P2P3P4P554P144P1P1451000s14RNGk-ε15Fig.4HydrogenConcentrationatFivePointsbyRNGk-εModel(Condition1)5a5baFLUENTk-00bRNGk-cGASFLOWdGASFLOWk-511000sFig.5HydrogenConcentrationFieldsat1000sbyDifferentTurbulenceModels(Condition1)Vol.28.No.1.20071025c5a5b5c5d5c5a5b6.5%5a5b8%45c5a5b5dRNGk-4.24.3RNGk-4.22kg/s10%90%6P1P2P3P4P552(22kg/s10%90%)6P1446P2300s4P2P2P3P4P56P1P24P3P4P56P14P171000s5b6RNGk-ε25Fig.6HydrogenConcentrationatFivePointsbyRNGk-εmodel(Condition2)721000sFig.7HydrogenConcentrationFieldsat1000s(Condition2)4.3100%0.5kg/s(3)8P1P2P3P4P558P1P2P3P4P5369400s3(200kg)1038RNGk-ε35Fig.8HydrogenConcentrationatFivePointsbyRNGk-εmodel(Condition3)9400s3Fig.9HydrogenConcentrationFieldsat400s(Condition3)95b75b7100%5(1)RNGε-kFLUENTε-kω-kGASFLOWε-kRNGε-k3GASFLOW(2)[1]BreitungW,ChanCK,DorofeevSB,etal.SOARonFlameAccelerationandDeflagration-to-DetonationTransitioninNuclearSafetyattheGroup’sFinalMeet-ingatFZK[C],Karlsruhe,1999.[2]Fluent6.0UserGuide[S],FluentInc,Lebanon,2001.[3]TravisJR,SporeJW,RoylP,etal.GASFLOW:AComputationalFluidDynamicsCodeforGases,Aero-solsandCombustion.Volumn1:theoryandComputa-tionalModel[S].FzKandLANL,2001.[4]TravisJR,SporeJW,RoylP,etal.GASFLOW:AComputationalFluidDynamicsCodeforGases,Aero-solsandCombustion.Volumn2:UserManual[S].FzKandLANL,2001.PrimaryStudiesonFactorsforHydrogenConcentrationDistributioninContainmentunderSevereAccidentsXIAOJian-junZHOUZhi-weiJINGXing-qingInstituteofNuclearandNewEnergyTechnologyTsinghuaUniversityBeijing100084ChinaAbstractThreefactorsthatmayaffectthehydrogenconcentrationdistributioninthecontainmentwereinvestigated.CalculationresultsbyFLUENTandGASFLOWwerecompared.TheresultsindicatethatRNGk-modelcanobtainbetterresultsinparameterfluctuationcausedbyturbulence,velocityfieldandhydro-genconcentrationfieldthantheothermodels.TheresultscalculatedbyalgebraicmodelinGASFLOWaredifferentfromtheotherresultsinthesimulationofmassdiffusion,momentumdiffusion,andparametersfluctuation.Theeffectsofsteamconcentrationandmassflowrateattheleakageonhydrogenconcentrationdistributionhavebeenalsoinvestigated.Theresultsindicatethattheyaretwoimportantfactorshavingef-Vol.28.No.1.2007104fectsonhydrogenconcentrationdistribution.Turbulencemodelingandsimulationofturbulentbuoyantjetsandplumes,whichneedfurtherstudy,areofimportanceinhydrogenconcentrationdistributioninthecon-tainmentundersevereaccidents.KeywordsSevereaccidentHydrogendistributionContainment(1978—)2006(1957—)1989(1940—)1963()(89)(5)2SafetyConsiderationinDesignofClosedLoopControlSystemforMiniatureNeutronSourceReactorCHENYu1GUOCheng-zhan1WANGLi-yu2SUNHui-bin1ZHAOHai-ge11.JointInstituteofAppliedNuclearTechnologyShenzhenUniversityGongdong518060China2.ChinaInstituteofAtomicEnergyBeijing102413ChinaAbstractTheconfigurationsofthenewclosed-loopcontrolsystemareintroducedbriefly.Thesystem,servedbytwocomputersconnectedwithLAN,ismadetocontrolMiniatureNeutronSourceReactor(MNSR)whichisbuiltinShenzhenUniversity.Thetechniquemeasuresanddesignpolestarsforpowercontrolandsafetyprotectingaredescribedinthepaper.Themeasuresincludetherestrictingofthebuilt-inreactivity,usingrightworkingmodelwithdualcontrolbars,usingcontrol-barsdroppingsysteminemergencies,settingtherightfactorsforworking/protection/emergencies,andtakingthecountermeasuresforpotentialrisks.Thepivotalvariablesarecheckedredundantlyandcouldbesharedbetweentwocomputers.Thisalsoenhancedthereliabilityofthesystemforthereactor.KeywordsMiniatureNeutronSourceReactor(MNSR)SafetyControlsystem(1957)1998(1941)1966(1942)1964()