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
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