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방인철

Bang, In Cheol
Nuclear Thermal Hydraulics and Reactor Safety Lab.
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dc.citation.conferencePlace CC -
dc.citation.title 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 -
dc.contributor.author Jeong, YS -
dc.contributor.author Kim, KM -
dc.contributor.author Kim, IG -
dc.contributor.author Bang, In Cheol -
dc.date.accessioned 2023-12-19T18:36:05Z -
dc.date.available 2023-12-19T18:36:05Z -
dc.date.created 2019-03-21 -
dc.date.issued 2017-09-03 -
dc.description.abstract Hybrid heat pipe, which is a combination of heat pipe and control rod takes a role of both criticality control and passive decay heat removal for dry cask. Hybrid heat pipe module by integrating canister lid with each rod was introduced as updated version of hybrid heat pipe-integrated dry cask, called UCAN. In this paper, recent design work of UCAN considering all functional requirements of dry storage facilities such as containment, radiation shielding, criticality control and thermal management was discussed. In terms of decay heat removal of dry cask, full scale UCAN and single hybrid heat pipe was analyzed by means of CFD simulation using ANSYS-CFX. As a result, hybrid heat pipe has 902.8 W heat removal capacity in normal dry storage condition for dry cask having 21 PWR spent nuclear fuel assemblies. Considering working principle and unique geometry of hybrid heat pipe, enhancement of maximum heat transfer capacity has been currently under developed. -
dc.identifier.bibliographicCitation 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 -
dc.identifier.issn 0000-0000 -
dc.identifier.scopusid 2-s2.0-85052397006 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/35103 -
dc.language 영어 -
dc.publisher The Chinese Nuclear Society (CNS) and Xi’an Jiaotong University (XJTU) -
dc.title Hybrid heat pipe module for dry cask with enhanced cooling for extended storage of spent nuclear fuel -
dc.type Conference Paper -
dc.date.conferenceDate 2017-09-03 -

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