Title of article :
Boilingwaterreactorwithinnovativesafetyconcept:TheGenerationIII+SWR-1000OriginalResearchArticle
Author/Authors :
ZoranV.Stosic، نويسنده , , WernerBrettschuh، نويسنده , , UweStoll، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2008
Pages :
39
From page :
1863
To page :
1901
Abstract :
AREVANPhasdevelopedaninnovativeboilingwaterreactor(BWR)SWR-1000inclosecooperationwithGermannuclearutilitiesandwithsupportfromvariousEuropeanpartners.ThisGenerationIII+reactordesignmarksanewerainthesuccessfultraditionofBWRand,withanetelectricaloutputofapproximately1250MWe,isaimedatensuringcompetitivepowergeneratingcostscomparedtogasandcoalfiredstations.Itisparticularlysuitableforcountrieswhosepowernetworkscannotfacilitatelargepowerplants.Atthesametime,theSWR-1000meetsthehighestsafetystandards,includingcontrolofcoremeltaccidents.Theseobjectivesaremetbysupplementingactivesafetysystemswithpassivesafetyequipmentofvariousdesignsforaccidentdetectionandcontrolandbysimplifyingsystemsneededfornormalplantoperationonthebasisofpastoperatingexperience.Theplantisalsoprotectedagainstairplanecrashloads. Thefunctionalcapabilitiesandcapacitiesofallnewsystemsandcomponentsweresuccessfullytestedunderrealisticandconservativeboundaryconditionsinlarge-scaletestfacilitiesinFinland,SwitzerlandandGermany. Ingeneral,theSWR-1000designisbasedonwell-provenanalyticalcodesanddesigntoolsvalidatedforBWRapplicationsthroughrecalculationofrelevantexperimentsandindependentlicensingactivitiesperformedbyauthoritiesortheirexperts.Theoverviewofusedanalyticalcodesanddesigntoolsaswellasperformedexperimentalvalidationprogramsispresented. Effectiveimplementationofpassivesafetysystemsisdemonstratedthroughthenumericalsimulationoftransientsandlossofcoolantaccidents(LOCAs)aswellasthroughanalyticalsimulationofasevereaccidentassociatedwiththecoremelt.IntheLOCAsimulationpresentedtheexistingactivecorefloodingsystemswerenotusedforemergencycontrol:onlypassivesystemswererelevantfortheanalyses.Despitethis–nocoreheat-upoccurred.Inthecaseofreactorcoremeltingnumericallyisdemonstratedthatthemoltencoredebriswouldberetainedinsidethereactorvesselduetotheeffectivepassiveexternalwatercoolingofthevessel,keepingitcompletelyintact. Ashortconstructionperiodofjust48monthsfromfirstconcretetoprovisionaltakeover,flexiblefuelcyclelengthsofbetween12and24monthsandahighfueldischargeburn-upallcontributetowardsmeetingeconomicgoals.Realisticaverageavailabilityforaplantlifetimeof60yearsand12monthscycleis94.5%.SystemsandplantdesignwerereviewedbyexpertgroupsofEuropeanutilities.WiththeSWR-1000,AREVANPhasdevelopedadesignconceptforaBWRplantthatisnowreadyforcommercialdeploymentandwhichfullymeetsthemoststringentinternationalrequirementsintermsofnuclearsafetyandnuclearregulatory.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2008
Journal title :
Nuclear Engineering and Design Eslah
Record number :
895143
Link To Document :
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