Full metadata record
DC Field | Value | Language |
---|---|---|
dc.contributor.author | 김성중 | - |
dc.date.accessioned | 2016-12-08T05:12:45Z | - |
dc.date.available | 2016-12-08T05:12:45Z | - |
dc.date.issued | 2015-05 | - |
dc.identifier.citation | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v. 52, NO 5, Page. 695-708 | en_US |
dc.identifier.issn | 0022-3131 | - |
dc.identifier.issn | 1881-1248 | - |
dc.identifier.uri | http://www.tandfonline.com/doi/full/10.1080/00223131.2014.978407 | - |
dc.identifier.uri | http://hdl.handle.net/20.500.11754/24751 | - |
dc.description.abstract | Severe 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.sponsorship | This 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.iso | en | en_US |
dc.publisher | TAYLOR & FRANCIS LTD | en_US |
dc.subject | in-vessel retention | en_US |
dc.subject | accident management | en_US |
dc.subject | MELCOR | en_US |
dc.subject | OPR1000 | en_US |
dc.subject | numerical simulation | en_US |
dc.subject | in-vessel mitigation | en_US |
dc.subject | severe accident | en_US |
dc.subject | hydrogen production | en_US |
dc.subject | RCS depressurization | en_US |
dc.subject | PWR-type reactor | en_US |
dc.title | Effectiveness and adverse effects of reactor coolant system depressurization strategy with various severe accident management guidance entry conditions for OPR1000 | en_US |
dc.type | Article | en_US |
dc.relation.no | 5 | - |
dc.relation.volume | 52 | - |
dc.identifier.doi | 10.1080/00223131.2014.978407 | - |
dc.relation.page | 695-708 | - |
dc.relation.journal | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | - |
dc.contributor.googleauthor | Seo, Seungwon | - |
dc.contributor.googleauthor | Lee, Yongjae | - |
dc.contributor.googleauthor | Lee, Seongnyeon | - |
dc.contributor.googleauthor | Kim, Hwan-Yeol | - |
dc.contributor.googleauthor | Kim, Sung Joong | - |
dc.relation.code | 2015002977 | - |
dc.sector.campus | S | - |
dc.sector.daehak | COLLEGE OF ENGINEERING[S] | - |
dc.sector.department | DEPARTMENT OF NUCLEAR ENGINEERING | - |
dc.identifier.pid | sungjkim | - |
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