Title of article
Analysisofalossofresidualheatremovalsystemduringmid-loopconditionsatPKLfacilityusingRELAP5/Mod3.3OriginalResearchArticle
Author/Authors
S.Carlos، نويسنده , , J.F.Villanueva، نويسنده , , S.Martorell، نويسنده , , V.Serradell، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
7
From page
2561
To page
2567
Abstract
Whenanuclearpowerplantisinshutdownconditionsforrefuelling,thereactorcoolantsystemwaterlevelisreduced.Thissituationisknownasmid-loopoperation,andtheresidualheatremoval(RHR)systemisusedinthissituationtoremovethedecaypowerheatgeneratedinthereactorcore.
Inmid-loopconditions,someaccidentalsituationsmayoccurwithnotanegligiblecontributiontotheplantrisk,andallinvolvethelossoftheRHRsystem.Thus,tobetterunderstandthethermal–hydraulicprocessesfollowingthelossoftheRHRduringshutdown,transientsofthiskindhavebeensimulatedusingbest-estimatecodesindifferentintegraltestfacilities.Thispaperfocusesonthesimulation,usingthebestestimatecodeRELAP5/Mod3.3,oftheexperimentE3.1conductedatthePKLfacility.ThisexperimentconsistsofthelossoftheRHRsystemwhentheplantisinmid-loopconditionsforrefuellingandwiththeprimarycircuitclosed.Inparticular,inthisexperimentthephysicalphenomenatoinvestigatearethemechanismsofheatremovalinpresenceofnitrogenandthedeborationincriticalpartsoftheprimarysystem.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
941501
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