• Title of article

    Risk-informeddesignguidanceforfuturereactorsystemsOriginalResearchArticle

  • Author/Authors

    MichaelJ.Delaney، نويسنده , , GeorgeE.Apostolakis، نويسنده , , MichaelJ.Driscoll، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2005
  • Pages
    20
  • From page
    1537
  • To page
    1556
  • Abstract
    Futurereactordesignsfaceanuncertainregulatoryenvironment.ItisanticipatedthattherewillbesomelevelofprobabilisticinsightsintheregulationsandsupportingregulatorydocumentsforGeneration-IVnuclearreactors.Centraltocurrentregulationsaredesignbasisaccidents(DBAs)andthegeneraldesigncriteria(GDC),whichwereestablishedbeforeprobabilisticriskassessments(PRAs)weredeveloped.Theseregulationsimplementastructuralistapproachtosafetythroughtraditionaldefenseindepthandlargesafetymargins.Inarationalistapproachtosafety,accidentfrequenciesarequantifiedandprotectivemeasuresareintroducedtomakethesefrequenciesacceptablylow.Bothapproacheshaveadvantagesanddisadvantagesandfuturereactordesignandlicensingprocesseswillhavetoimplementahybridapproach.Thispaperpresentsaniterativefour-steprisk-informedmethodologytoguidethedesignoffuture-reactorsystemsusingagas-cooledfastreactoremergencycorecoolingsystemasanexample.Thismethodologyhelpsdesignerstoanalyzealternativedesignsunderpotentialrisk-informedregulationsandtoanticipatedesignjustificationstheregulatormayrequireduringthelicensingprocess.Theanalysisdemonstratedtheimportanceofcommon-causefailuresandtheneedforguidanceonhowtochangethequantitativeimpactofthesepotentialfailuresonthefrequencyofaccidentsequencesasthedesignchanges.Deliberationisanimportantpartofthefour-stepmethodologybecauseitsupplementsthequantitativeresultsbyallowingtheinclusioninthedesignchoiceofelementssuchasbestdesignpracticesandeaseofonlinemaintenance,whichusuallycannotbequantified.Thecasestudyshowedthat,insomeinstances,thestructuralistandtherationalistapproacheswereinconsistent.Inparticular,GDC35treatsthedouble-endedbreakofthelargestpipeinthereactorcoolantsystemwithconcurrentlossofoffsitepowerandasinglefailureinthemostcriticalplaceastheDBAfortheemergencycorecoolingsystem.Seventeenoutofthe45variationsthatweconsideredviolatedthisDBA,butpassedtheprobabilisticscreeningcriteria.UsingPRAtechniques,wefoundthatthemeanfrequencyofthisaccidentwasverylow,thusindicatingthatdeterministiccriteriasuchasGDC35mustbereassessedinthelightofriskinsights.
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2005
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    894941