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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.conferencePlace US -
dc.citation.endPage 1426 -
dc.citation.startPage 1416 -
dc.citation.title 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 -
dc.contributor.author Kim, KM -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2024-02-01T00:06:01Z -
dc.date.available 2024-02-01T00:06:01Z -
dc.date.created 2020-01-29 -
dc.date.issued 2019-08-18 -
dc.description.abstract Various passive safety systems have been designed for the improved safety of nuclear reactors, however, feasibility of limited number of newly suggested safety systems has been evaluated, because there is limited applicability on integral effect test facilities. In addition, research activities combining 4th industrial revolution technologies and operation technologies of nuclear power plants have difficulties in real test and evaluating the feasibility. In this study, an integral effect test facility, nuclear power plant innovation platform, was constructed with three-level scaling method proposed by Ishii and Kataoka, to provide easy applicability on newly suggested technologies. It is a 1/8-height and 1/1152-volume scaled test facility with respect to APR-1400. In addition, it consists of visualization parts (glass) and 3D printed components to improve the utilization of integral test facility. In this paper, detail design process and specifications of nuclear power plant innovation platform including its utilizations were described. Through the series of experiments with the constructed test facilities, the system behaviors of reference reactor under the simulated normal operation condition and station blackout condition will be observed including specific thermal-hydraulic phenomena in the system by visualization parts. -
dc.identifier.bibliographicCitation 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, pp.1416 - 1426 -
dc.identifier.issn 0000-0000 -
dc.identifier.scopusid 2-s2.0-85073744455 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/79383 -
dc.language 영어 -
dc.publisher American Nuclear Society -
dc.title Integral effect tests in visualization basis 3D printed test facility for improved applicability of innovative technologies -
dc.type Conference Paper -
dc.date.conferenceDate 2019-08-18 -

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