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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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Integral effect tests in visualization basis 3D printed test facility for improved applicability of innovative technologies

Author(s)
Kim, KMBang, In Cheol
Issued Date
2019-08-18
URI
https://scholarworks.unist.ac.kr/handle/201301/79383
Citation
18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, pp.1416 - 1426
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.
Publisher
American Nuclear Society
ISSN
0000-0000

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