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dc.contributor.author제무성-
dc.date.accessioned2019-12-04T01:13:48Z-
dc.date.available2019-12-04T01:13:48Z-
dc.date.issued2018-01-
dc.identifier.citationJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, v. 55, no. 7, page. 691-702en_US
dc.identifier.issn0022-3131-
dc.identifier.issn1881-1248-
dc.identifier.urihttps://www.tandfonline.com/doi/full/10.1080/00223131.2018.1428123-
dc.identifier.urihttps://repository.hanyang.ac.kr/handle/20.500.11754/116974-
dc.description.abstractNuclear power plants in Korea are preparing improvement countermeasures for severe accidents including mobile gas turbine generators, passive autocatalytic recombiners, containment-filtered venting systems, and external injection using portable pumps. However, these improvement countermeasures have only been determined by expert judgment, and detailed validation of their effects has not been performed. In this paper, the quantitative safety impact of these improvement countermeasures was evaluated for the Westinghouse 3-loop pressurized water reactor. Our evaluation of four improvement countermeasures using the at-power internal event probabilistic safety assessment models revealed that all containment failure modes have positive effects, except for the containment isolation failure and the containment bypass. Therefore, post-Fukushima action plans for coping with a severe accident in Korea have been appropriately evaluated and established.en_US
dc.description.sponsorshipThis work was supported by the Nuclear Safety Research Program through the Korea Foundation Of Nuclear Safety (KOFONS), granted financial resource from the Multi-Unit Risk Research Group, Republic of Korea (No. 1705001).en_US
dc.language.isoen_USen_US
dc.publisherTAYLOR & FRANCIS LTDen_US
dc.subjectProbabilistic safety assessmenten_US
dc.subjectcontainment-filtered venting systemen_US
dc.subjectquantitative safety impacten_US
dc.subjectsevere accidenten_US
dc.subjectcontainment failureen_US
dc.titleQuantitative assessment of severe accident management strategies in a nuclear power planten_US
dc.typeArticleen_US
dc.relation.no7-
dc.relation.volume55-
dc.identifier.doi10.1080/00223131.2018.1428123-
dc.relation.page691-702-
dc.relation.journalJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-
dc.contributor.googleauthorJung, Gunhyo-
dc.contributor.googleauthorJae, Moosung-
dc.relation.code2018003158-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidjae-
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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