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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.conferencePlace JA -
dc.citation.title 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 -
dc.contributor.author Shirvan, K -
dc.contributor.author Kim, Ji Hyun -
dc.contributor.author Hwang, IS -
dc.contributor.author Ballinger, R -
dc.date.accessioned 2023-12-19T19:08:25Z -
dc.date.available 2023-12-19T19:08:25Z -
dc.date.created 2019-03-21 -
dc.date.issued 2017-04-24 -
dc.description.abstract Light Water Reactor Small Modular Reactors (LWR SMRs) have struggled to penetrate the US and international electricity markets while solar and wind energy have experienced tremendous success. Lead Fast Reactor (LFR) technology has great potential as an alternative to LWR SMRs to be able to complement solar and wind energy to produce baseload carbon free electricity. The inherent properties of lead coolant results in high degree of safety, plant simplification and design compactness. This study focuses on thermal-hydraulic performance of a natural circulating Lead-Bismuth Eutectic (LBE) cooled reactor with passive air cooling safety system. Specifically, the LFR design's response during steady state and ultimate loss of heat sink accident to thermal hydraulic model perturbations is shown to be insensitive. -
dc.identifier.bibliographicCitation 2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 -
dc.identifier.issn 0000-0000 -
dc.identifier.scopusid 2-s2.0-85036464302 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/34957 -
dc.language 영어 -
dc.publisher International Congress on Advances in Nuclear Power Plants, ICAPP -
dc.title System level thermal-hydraulic assessment of a natural circulating LFR -
dc.type Conference Paper -
dc.date.conferenceDate 2017-04-24 -

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