Title of article
Post-irradiationexaminationsfocusedonfuelintegrityofspentBWR-MOXandPWR-UO2fuelsstoredfor20yearsOriginalResearchArticle
Author/Authors
A.Sasahara، نويسنده , , T.Matsumura، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
10
From page
1250
To page
1259
Abstract
Post-irradiationexaminations(PIEs)ofspentBWR-MOXandPWR-UO2fuelrodsirradiatedincommercialLWRsandstoredfor20yearswerecarriedouttoevaluatefuelintegrityduringstorage.Averageburn-upoffivefuelrodsoftheBWR-MOXfuelwasabout20MWd/kgHMandthatofthePWR-UO2fuelwas58MWd/kgHM.ThePIEitemsincluded:(a)visualinspectionofthecladdingsurface,(b)puncturetest,(c)ceramographicobservationonthepelletandcladding,(d)pelletdensity,(e)electronprobemicroanalysisofthepellet,(f)claddingtensiletest,(g)hydrogencontentandhydrideorientationinthecladding,and(h)hydrogenredistributioninthecladdingundertemperaturegradient.ThePIEresultsshowednomarkeddifferenceinthevisualinspection,fissiongasrelease,oxidelayerthickness,pelletmicrostructure,andcladdingmechanicalpropertiesorhydrideorientationafterstorage.Theresultofthehydrogenredistributionexperimentshowedthathydrogenmigrationhadlittleeffectonthefuelintegrityduringdrystorage.Hydrogenmigrationonthefuelrodfor40yearsofstoragewasevaluatedusingtheheatoftransportobtainedinthehydrogenredistributionexperimentandcalculatedresultshowedthathydrogenmigrationhadlittleeffectonthefuelintegrityduringdrystorage.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
895084
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