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신명수

Shin, Myoungsu
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dc.citation.conferencePlace KO -
dc.citation.conferencePlace 강릉 -
dc.citation.endPage 119 -
dc.citation.startPage 118 -
dc.citation.title 한국구조물진단유지관리공학회 2019년 봄 학술발표회 -
dc.contributor.author 김승필 -
dc.contributor.author 신명수 -
dc.contributor.author 손동성 -
dc.contributor.author 권혁주 -
dc.date.accessioned 2024-02-01T00:37:06Z -
dc.date.available 2024-02-01T00:37:06Z -
dc.date.created 2019-09-25 -
dc.date.issued 2019-04-11 -
dc.description.abstract This study examined the safety of nuclear spent-fuel (NSF) transport casks against accidental puncture events. Finite element analyses were conducted according to the accident conditions in NUREG-1536 and RG 7.8, which specify 1-m parallel and vertical drops on a rigid rod that has 15-cm diameter and 20-cm height. We focused on the safety evaluation of the cask body, baskets, and canister based on ASME BPVC Section III, and evaluated whether these elements would undergo excessive fracture or puncture. -
dc.identifier.bibliographicCitation 한국구조물진단유지관리공학회 2019년 봄 학술발표회, pp.118 - 119 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/80024 -
dc.language 한국어 -
dc.publisher 한국구조물진단유지관리공학회 -
dc.title.alternative Safety evaluation of nuclear spent-fuel transport casks in puncture events -
dc.title 사용후핵연료 운송용기의 관통 안전성 평가 -
dc.type Conference Paper -
dc.date.conferenceDate 2019-04-10 -

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