秦山核电二期扩建工程严重事故对策分析

上海交通大学硕士学位论文秦山核电二期扩建工程严重事故对策分析姓名：刘明章申请学位级别：硕士专业：核能与核技术工程指导教师：曹学武;商幼明20080201VI2004418HAF1021#2#“”PSAPSA1VII231LOFWSBOLOCA6502LOCALOCASBO3EUF65VIIIQinshan-IIExtensionProjectSevereAccidentCountermeasureAnalysisABSTRACTThefrequencyofthesevereaccidenthappenedinNPPisrarelylow,onceitoccurred,itwillbringsonverysevereresult,thesevereaccidenthadbeenoccurredinhistoricalarmedus,itisnon-abundantthatnuclearsafetyonlyconsidersdesignbasicaccident,wemustconsiderthepreventingandmitigatingofthesevereaccidenttomeetwiththeincreasingrequirementofenergyandsafety.Inthe“nuclearpowerplantdesignsafetyregulation”(HAF102)issuedbyNationNuclearSafetyAdministration(NNSA),April18,2004,aimatthepreventingandmitigatingofsevereaccident,theregulationbringforwardnewrequirement,whichrequiredthatduringdesignphase,NPPshouldconsidersettingthepreventingandmitigationmeasurementofsevereaccidentasactuallyaspossible.Qinshan-IIextensionprojectisbaseduponQinshan-II(unit1&2)andabidesby“replicateandimprovement”principle.Aimatthesevereaccident,sincethePSAofQinshan-IIextensionprojectisnotcompleted,can’tusethePSAresulttoanalyzethesevereaccident,sowerefertotherelatingsafetystudyandthepracticeofthesimilarnuclearpowerplant,IXthroughanalysisandcomparing,basisreasonableandfeasibletosetthepreventingandmitigationmeasurementofsevereaccidentasactuallyaspossible.Accordingtheinternationaluniversalsevereaccidentchoosingprinciple,thispaperconfirmedtheelevenaccidentsequenceswhichcouldresultQinshan-IIEPinsevereaccident,andcalculatingandanalyzingtheeachsevereaccidentsequence.Accordingtheresultofthesevereaccidentcalculating&analyzing,referencingtherelatingexperienceofthedomesticandoverseaplantandcombinetheobjectoftheaccidentmitigation,Qinshan-IIEPadoptedthreeitemssevereaccidentmitigationmeasurement:1.Adoptingpressurizerdepressurizationfunctionextensiontopreventthehigh-pressurecoremeltresultingindirectheatingcontainment;2.InstallingEUHsystemtopreventinghydrogenburning;3.Installingcontainmentfiltrateexhaustsystem(EUF)topreventthecontainmentfailedonover-pressure.Thispaperapplythesevereaccidentanalyzingprogramtocomparinganalyzethesequencewhichcouldmakehigh-pressurecoremelt,hydrogenburningandcontainmentfailedinover-pressure,andwhichisthebiggestcoredamagefrequency,andthefollowingisthemainconclusion:1.InLOFWaccident,SBOaccidentandSBLOCAaccident,adoptingtheXmeasurethattheoperatorsopenedthepressurizersafetyvalvetodepressurization.Whenthepressurevesselfailed,themeasurecouldreducethepressureofthefirstloopavailably,andthenmitigatetheriskofthehigh-pressurecoremeltedresultedincontainmentdirectheating.2.Qinshan-IIEPinstalledtheEUHsystemincontainment,whichcouldcompositetheplentifulhydrogenproductedinSBLOCA,LBLOCAandSBOaccident.Theconcentrationofhydrogenincontainmentmaintainsthelowlevel,whichavailablyrestricttheriskofhydrogenburning.3.Qinshan-IIEPcontainmentfiltrateexhaustsystem(EUF)couldmitigatetheincreasingofcontainmentpressureafterthesevereaccidentoccurred,thateliminatedtheriskofcontainmentslowlyover-pressuredeffectively.ThroughanalyzingthesevereaccidentsequenceofQinshan-IIEP650MWenuclearpowerplantthispaperputforwardthesevereaccidentmitigatingmeasureforplant,anddemonstratingthevalidityofthesevereaccidentmitigatingmeasurebysevereaccidentanalyses.ItisveryimportantfortheQinshan-IIEPtoadvancethesafetyperformance,anditwillputforwardthespecificwayforthenextphases’investigatingwork,anditalsohasmagnitudesignificantreferencemeritforthenewnuclearpowerplanttodothesimilarworkinfuture.Keywords:nuclearpowerplant,severeaccident,preventingandmitigation,accidentmanagementIII20080218IV□□√“√”20080218110-4/·10-5/·20801.11.1.18019791975WASH-14001979NRC[2-5]19858NRC50FR32138[6]“”219888NRCGL8820IPENRC19898199041990719916GL8820GL8820S1S4IPEAMCPIIPEEENRC1993IPEIPEEE199719961997NRCIPENUREG1560IPE19905PSANUREG1150[7-11]IPENRCNRCIPENRCCPI1989NRCSAMAsNRC[12]NRCNRC1992EPRISAMGsEOP1994114NEI91-0415“”3IPEIPEEESAMGSAMG8090NEANuclearEnergyAgency1991199520012001SAMNEANEASAM2008[13]JAERIALPHAVEGAWIND20001991~19951996~2000JAERI199119941999“19941998”SAMGPRA4PRASAMGIAEA[14]2002IAEA1.1.211[15,16]SAMG2002858[17]DBA510−610−[18-21]1.21.2.1NRCIAEANEANEARCS3RCS65RCS2PWR1012345678910PWR1RWST234AC1RCPRCSRCS7SG23RCSDCH456RCS7RCSSG1.2.2[15-18]LOCASGTRMELCORLOCASBOMELCORSCDAP/RELAP5CONTAINSAMGMELCORSBOSAMGEOPSAMGPSA8RELAP5/MOD2MARCH3SGTRRELAP5MARCH3SGTRSGTR403sSGSGSGTRSGTR1.2610-6/RCPRCPMELCORKORIGENPSAICARE2V2mod2.31%2%RELAP5/MOD2LOCASGTRSBO91.3WOGSAMG(WestinghouseOwnersGroupSevereAccidentManagementGuideline)TSC(TechnicalSupportCenter)SACRGsDFCSAGsSCSTSCGsSAEGsCAs[22-24]DFCRCS(ReactorCoolantSystem)RCSRCS1.3.11EPRITBR[25-29]NRCNEIEPRI(SAMGTBR)[15]SAMGSAM“RCS”“”:////102WOGSAMG[30-35]WOGSAMGEPRITBR,TSCTSCWOGSAMGSACRGs,SACRG-1SACRG-2SACRG-1TSCEOPSACRG-2TSCTSCTSCDFCSAGsDFCSAGSAGsSAG-1SAG-2SAG-3SAG-4SAG-5SAG-6SAG-7SAG-8RCS11SCSTSCGsSCSTSCGsDFCSAGsTSCDFCSCSTSCSTSCGsSCG-1SCG-2SCG-3SCG-4SCGsSCG-15SAEGs12SAEG-1SAEG-2SAEG-1SAEG-2SAMGCAsCA-1CA-2CA-3CA-4CA-5CA-6CA-73CEOGAMGABBCEROGEPRITBRABBCETSC/AMGEPRITBRRCS/RCS4AMRSKGRSRSK135USAMGEDFSAMGSPISPUU1U5R