Title of article :
Boilingwaterreactorwithinnovativesafetyconcept:TheGenerationIII+SWR-1000OriginalResearchArticle
Author/Authors :
ZoranV.Stosic، نويسنده , , WernerBrettschuh، نويسنده , , UweStoll، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2008
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
Journal title :
Nuclear Engineering and Design Eslah