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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.endPage 1051 -
dc.citation.number 3 -
dc.citation.startPage 1037 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 56 -
dc.contributor.author Kim, Ji Yong -
dc.contributor.author Yoo, Seung Chang -
dc.contributor.author Seo, Joo Hyung -
dc.contributor.author Kim, Ji Hyun -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2024-05-03T17:05:13Z -
dc.date.available 2024-05-03T17:05:13Z -
dc.date.created 2024-04-29 -
dc.date.issued 2024-03 -
dc.description.abstract This paper presents the construction results and design of the UNIST Reactor Innovation platform for small modular reactors as a versatile testbed for exploring innovative technologies. The platform uses simulant fluids to simulate the thermal-hydraulic behavior of a reference small modular reactor design, allowing for cost-effective design modifications. Scaling analysis results for single and two-phase natural circulation flows are outlined based on the three-level scaling methodology. The platform's capability to simulate natural circulation behavior was validated through performance calculations using the 1-D system thermal-hydraulic code-based calculation. The strategies for evaluating cutting-edge technologies, such as the integration of a solid oxide electrolysis cell for hydrogen production into a small modular reactor, are presented. To overcome experimental limitations, the hardware-in-the-loop technique is proposed as an alternative, enabling real-time simulation of physical phenomena that cannot be implemented within the experimental facility's hardware. Overall, the proposed versatile innovation platform is expected to provide valuable insights for advancing research in the field of small modular reactors and nuclear-based hydrogen production. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.56, no.3, pp.1037 - 1051 -
dc.identifier.doi 10.1016/j.net.2023.12.047 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-85181253766 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/82326 -
dc.identifier.wosid 001202788300001 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Design and construction of fluid-to-fluid scaled-down small modular reactor platform: As a testbed for the nuclear-based hydrogen production -
dc.type Article -
dc.description.isOpenAccess TRUE -
dc.relation.journalWebOfScienceCategory Nuclear Science & Technology -
dc.relation.journalResearchArea Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.description.journalRegisteredClass kci -
dc.subject.keywordAuthor Small modular reactor (SMR) -
dc.subject.keywordAuthor Scaling analysis -
dc.subject.keywordAuthor Nuclear innovation platform -
dc.subject.keywordAuthor URI-SMR -
dc.subject.keywordAuthor Nuclear -hydrogen -
dc.subject.keywordPlus HYBRID HEAT-PIPE -
dc.subject.keywordPlus PRESSURIZED WATER-REACTOR -
dc.subject.keywordPlus THERMAL-HYDRAULIC SYSTEM -
dc.subject.keywordPlus CORE COOLING SYSTEM -
dc.subject.keywordPlus ENERGY SYSTEM -
dc.subject.keywordPlus TEST FACILITY -
dc.subject.keywordPlus CONTROL ROD -
dc.subject.keywordPlus OPERATION -
dc.subject.keywordPlus INSTABILITIES -
dc.subject.keywordPlus COGENERATION -

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