Title of article
Thethree-dimensionalneutronkineticscoupledwiththermal-hydraulicsinRBMKaccidentanalysisOriginalResearchArticle
Author/Authors
F.D’Auria، نويسنده , , S.Soloviev، نويسنده , , V.Malofeev، نويسنده , , K.Ivanov، نويسنده , , C.Parisi، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
24
From page
1002
To page
1025
Abstract
TheRBMKcoreisacomplexensembleofhigh-pressurehigh-temperaturetubes,graphitebricks,low-pressurelow-temperaturecontrolrodtubes,graphiteinterstitialgaspassages.Anabout7MPaboilinglightwatercrossesthearound19mlongverticaltubes(7mactivelength).Thelatticeconsistingofgraphitecolumnsandhydraulicchannelsisboundedbythereactorcavitywhoseresistantelementsarethemetalcylindricaltankandthickcirculartopandbottomplateswithproperholesforthepassageoftubes.
Relatedtoatypicalwatercooledreactor,thepeculiaritiesoftheRBMKcorecanbesummarizedasfollows:(a)largedimensions–theoverallcorevolumeisbyfarthelargestforanuclearpowerplant(NPP)producingelectricity;(b)useofseparatemoderatorandcoolantconstitutedbygraphiteandlightboilingwater,respectively–theboilingwatermostlyabsorbsneutronsinthisenvironmentleadingtothe(small)positivevoidreactivitycoefficient;(c)presenceofwaterchannelsveryclosetoeachothercontainingcoolantatdifferenttemperatures(543–557Kand350Kforfuelchannels(FC)andcontrolandprotectionsystem(CPS)channels,respectively);(d)presenceofcore-wideradial,core-wideaxialandlocaltemperaturegradientsinthegraphitebrickswithtemperaturevaluesintherange330–650Kwiththehigh-temperaturevaluesjustifiedbytheneutronmoderationandgamma-heatingprocesses.
Owingtotheabovepeculiarities,thedevelopmentandtheuseofathree-dimensionalneutronkineticscode(3DNK)coupledwithaone-dimensionalthermal-hydraulic(TH)codeisessentialinRBMKsafetyanalyses.
Twoapproacheshavebeenusedwithinthepresentcontext,i.e.useofcoupled3DNK-THcodestosupporttheaccidentanalysisintheRBMKasdiscussedinthefirstofthecompanionpapersinthisjournalvolume:applicationofKorsar-BarsmakinguseoftheUnkcodetoderiveλ-matricesneededforBarsandofRelap5/3D-NestlemakinguseoftheHelioscodetoderivethemacroscopiccross-sections.
Boundingtransientanalysesofaccidentscenariosincludingcontrolrodwithdrawal,variousLossofCoolantAccident(LOCA)anddischargeofthecontrolrodcircuit,havebeencompleted.Inalloftheanalysedcases,startingfromnominaloperatingconditions,modestfissionpowertimegradientshavebeenfound,i.e.characterizedbytimederivativevaluesforlocalandglobalpowerchangessubstantiallysmallerthancurrentvaluesacceptedinsafetyanalysesoflightwaterreactors.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
895060
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