Title of article :
AnalysisofMOXfuelbehaviorinreduced-moderationwaterreactorbyfuelperformancecodeFEMAXI-RMOriginalResearchArticle
Author/Authors :
MotoeSuzuki، نويسنده , , HiroakiSaitou، نويسنده , , TakamichiIwamura، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2004
Abstract :
Toassessthefeasibilityofthe31%Pu-MOXfuelroddesignofreduced-moderationwaterreactor(RMWR)intermsofthermalandmechanicalbehaviors,asinglerodassumedtobeirradiatedinthecoreofRMWRupto106GWd/tHMhasbeenanalyzedbyafuelperformancecodeFEMAXI-RMwhichisanextendedversionofFEMAXI-6code.Intheanalysis,designspecificationsoffuelrodandirradiationconditionshavebeeninput,andavailablemodelsofbothMOXfuelandUO2fuelhavebeenusedasappropriate.Theresultsare:fissiongasreleaseisseveraltensofpercent,rodinternalpressuredoesnotexceedthecoolantpressure,andthehighestfuelcentertemperatureis2400K,whilecladdingdiameterincreasecausedbypelletswellingiswithin1%strain.ThesepredictionssuggestthattheMOXfuelrodintegritywillbeheldduringirradiationinRMWR,thoughactualbehaviorofMOXpelletswellingandcladdingoxidationrequiretobeinvestigatedindetail.
Journal title :
Nuclear Engineering and Design Eslah
Journal title :
Nuclear Engineering and Design Eslah
