Title of article
AnalysisofMOXfuelbehaviorinreduced-moderationwaterreactorbyfuelperformancecodeFEMAXI-RMOriginalResearchArticle
Author/Authors
MotoeSuzuki، نويسنده , , HiroakiSaitou، نويسنده , , TakamichiIwamura، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2004
Pages
9
From page
19
To page
27
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
Serial Year
2004
Journal title
Nuclear Engineering and Design Eslah
Record number
894639
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