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김지현

Kim, Ji Hyun
UNIST Nuclear Innovative Materials Lab.
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dc.citation.startPage 153011 -
dc.citation.title JOURNAL OF NUCLEAR MATERIALS -
dc.citation.volume 552 -
dc.contributor.author Jung, Yunsong -
dc.contributor.author Lee, Yunju -
dc.contributor.author Kim, Ji Hyun -
dc.contributor.author Ahn, Sangjoon -
dc.date.accessioned 2023-12-21T15:37:30Z -
dc.date.available 2023-12-21T15:37:30Z -
dc.date.created 2021-06-10 -
dc.date.issued 2021-08 -
dc.description.abstract Accelerated corrosion tests of Al-B4C neutron absorber, equivalent to 37 months in a spent nuclear fuel pool, were conducted on three different period-installed surveillance coupons (33, 52, and 92 months) to further investigate the underlying mechanisms of premature surface corrosion and 10 B depletion which we had recently reported in another study. Microstructure characterization, electrochemical analysis, and neutron attenuation tests were conducted after the corrosion tests, and two types of galvanic corrosion, Al matrix/stainless steel and Al matrix/B4C particles, were discovered. The duplex oxide layer comprised of amorphous oxide and Al(OH)(3) films and pit corrosion were also observed on the surface with reduced densities (< 1%). The neutron attenuation tests on the absorbers and ICP-MS measurement of the coolant showed no considerable change in 10 B areal density. (C) 2021 Elsevier B.V. All rights reserved. -
dc.identifier.bibliographicCitation JOURNAL OF NUCLEAR MATERIALS, v.552, pp.153011 -
dc.identifier.doi 10.1016/j.jnucmat.2021.153011 -
dc.identifier.issn 0022-3115 -
dc.identifier.scopusid 2-s2.0-85105691750 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/53026 -
dc.identifier.url https://www.sciencedirect.com/science/article/pii/S0022311521002348?via%3Dihub -
dc.identifier.wosid 000653052500005 -
dc.language 영어 -
dc.publisher ELSEVIER -
dc.title Accelerated corrosion tests of Al-B4C neutron absorber used in spent nuclear fuel pool -
dc.type Article -
dc.description.isOpenAccess FALSE -
dc.relation.journalWebOfScienceCategory Materials Science, Multidisciplinary; Nuclear Science & Technology -
dc.relation.journalResearchArea Materials Science; Nuclear Science & Technology -
dc.type.docType Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.subject.keywordAuthor Spent nuclear fuel pool -
dc.subject.keywordAuthor Al-B4C neutron absorber -
dc.subject.keywordAuthor Accelerated corrosion tests -
dc.subject.keywordAuthor Radiation-assisted corrosion -
dc.subject.keywordAuthor Helium bubble -
dc.subject.keywordPlus COMPOSITE -
dc.subject.keywordPlus STABILITY -
dc.subject.keywordPlus BEHAVIOR -

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