Title of article
QuantificationofsevereaccidentsourcetermsofaWestinghouse3-loopplantOriginalResearchArticle
Author/Authors
Sang-MinLee، نويسنده , , Yu-ChihKo، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 2008
Pages
13
From page
1080
To page
1092
Abstract
IntegratedsevereaccidentanalysiscodesareusedtoquantifythesourcetermsoftherepresentativesequencesidentifiedinPSAstudy.Thecharacteristicsofthesesourcetermsdependonthedetaildesignoftheplantandtheaccidentscenario.Ahistoricalperspectiveofradioactivesourcetermisprovided.ThegroupingofradionuclidesindifferentsourcetermsorsourcetermquantificationtoolsbasedonTID-14844,NUREG-1465,andWASH-1400iscompared.TheradionuclidesreleasephenomenaandmodelsadoptedintheintegratedsevereaccidentanalysiscodesofSTCPandMAAP4aredescribed.Inthepresentstudy,thesevereaccidentsourcetermsforriskquantificationofMaanshanNuclearPowerPlantofTaiwanPowerCompanyarequantifiedusingMAAP4.0.4code.Amethodologyisdevelopedtoquantifythesourcetermsofeachsourcetermcategory(STC)identifiedintheLevelIIPSAanalysisoftheplant.Thecharacteristicsofsourcetermsobtainedarecomparedwithothersourceterms.TheplantanalyzedemploysaWestinghousedesigned3-looppressurizedwaterreactor(PWR)withlargedrycontainment.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
2008
Journal title
Nuclear Engineering and Design Eslah
Record number
895063
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