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안상준

Ahn, Sangjoon
UNIST RAdioactive NUclear Materials Lab.
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dc.citation.conferencePlace US -
dc.citation.conferencePlace Washington, D.C. -
dc.citation.endPage 245 -
dc.citation.startPage 244 -
dc.citation.title 2023 ANS Winter Conference and Expo -
dc.contributor.author Ha, Woong -
dc.contributor.author Ahn, Sangjoon -
dc.date.accessioned 2024-01-02T14:05:10Z -
dc.date.available 2024-01-02T14:05:10Z -
dc.date.created 2024-01-02 -
dc.date.issued 2023-11-15 -
dc.description.abstract INTRODUCTION
The Al-B4C metal matrix composite (MMC) type neutron absorber has been widely used in temporary and interim storage of spent nuclear fuel (SNF) to maintain neutron flux and criticality below safety regulatory limit. Expansion and extension of neutron absorber application become inevitable due to delay in SNF final disposal in few nuclear power generating countries. However, unexpected
premature degradation has been reported from surveillance coupons of a Al-B4C absorber used in spent nuclear fuel
pools (SFPs) [1]. Numerous helium bubbles observed at the interface between Al matrix and B4C particles suggested
10 B(n, α)7Li reactions as the major radiation damage mechanism [1].Radiation damage induced by 10B(n, α)7Li reaction in the
neutron absorber during dry SNF storage (at high temperature) has not yet been extensively studied. In this study, radiation
damage in Al-B4C neutron absorber was experimentally emulated by utilizing in-situ high-temperature heavy ion
beam irradiation with exponentially increasing dose levels up to 1 displacement per atom (dpa) at high temperatures up to
400 °C.
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dc.identifier.bibliographicCitation 2023 ANS Winter Conference and Expo, pp.244 - 245 -
dc.identifier.issn 0003-018X -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/67478 -
dc.language 영어 -
dc.publisher American Nuclear Society -
dc.title Emulation of Radiation Damage in Neutron Absorber under Dry Storage Environments -
dc.type Conference Paper -
dc.date.conferenceDate 2023-11-12 -

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