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dc.contributor.author김성중-
dc.date.accessioned2016-12-08T05:12:45Z-
dc.date.available2016-12-08T05:12:45Z-
dc.date.issued2015-05-
dc.identifier.citationJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v. 52, NO 5, Page. 695-708en_US
dc.identifier.issn0022-3131-
dc.identifier.issn1881-1248-
dc.identifier.urihttp://www.tandfonline.com/doi/full/10.1080/00223131.2014.978407-
dc.identifier.urihttp://hdl.handle.net/20.500.11754/24751-
dc.description.abstractSevere accident analysis for Korean OPR1000 with MELCOR 1.8.6 was performed by adapting a mitigation strategy under different entry conditions of Severe Accident Management Guidance (SAMG). The analysis was focused on the effectiveness of the mitigation strategy and its adverse effects. Four core exit temperatures (CETs) were selected as SAMG entry conditions, and Small Break Loss of Coolant Accident (SBLOCA), Station Blackout (SBO), and Total Loss of Feed Water (TLOFW) were selected as postulated scenarios that may propagate into severe accidents. In order to delay reactor pressure vessel (RPV) failure, entering the SAMG when the CET reached 923K, 923K, and 753K resulted in the best results for SBLOCA, SBO, and TLOFW scenarios, respectively. This implies that using event-based diagnosis for severe accidents may be more beneficial than using symptom-based diagnosis. There is no significant difference among selected SAMG entry conditions in light of the operator's available action time before the RPV failure. Potential vulnerability of the RPV due to hydrogen generation was analyzed to investigate the foreseeable adverse effects that act against the accident mitigation strategies. For the SBLOCA cases, mitigation cases generated more hydrogen than the base case. However, the amount of hydrogen generated was similar between the base and mitigation cases for SBO and TLOFW. Hydrogen concentrations of containment were less than 5% before RPV failure for most cases.en_US
dc.description.sponsorshipThis work was supported by National Research Foundation of Korea (NRF) grants funded by MISP [grant number NRF-2012M2B2A6029184], [grant number NRF-2014M2A8A4021295].en_US
dc.language.isoenen_US
dc.publisherTAYLOR & FRANCIS LTDen_US
dc.subjectin-vessel retentionen_US
dc.subjectaccident managementen_US
dc.subjectMELCORen_US
dc.subjectOPR1000en_US
dc.subjectnumerical simulationen_US
dc.subjectin-vessel mitigationen_US
dc.subjectsevere accidenten_US
dc.subjecthydrogen productionen_US
dc.subjectRCS depressurizationen_US
dc.subjectPWR-type reactoren_US
dc.titleEffectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000en_US
dc.typeArticleen_US
dc.relation.no5-
dc.relation.volume52-
dc.identifier.doi10.1080/00223131.2014.978407-
dc.relation.page695-708-
dc.relation.journalJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-
dc.contributor.googleauthorSeo, Seungwon-
dc.contributor.googleauthorLee, Yongjae-
dc.contributor.googleauthorLee, Seongnyeon-
dc.contributor.googleauthorKim, Hwan-Yeol-
dc.contributor.googleauthorKim, Sung Joong-
dc.relation.code2015002977-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidsungjkim-
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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