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
Link To Document :
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