dc.citation.conferencePlace |
KO |
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dc.citation.conferencePlace |
강릉 |
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dc.citation.endPage |
119 |
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dc.citation.startPage |
118 |
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dc.citation.title |
한국구조물진단유지관리공학회 2019년 봄 학술발표회 |
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dc.contributor.author |
김승필 |
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dc.contributor.author |
신명수 |
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dc.contributor.author |
손동성 |
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dc.contributor.author |
권혁주 |
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dc.date.accessioned |
2024-02-01T00:37:06Z |
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dc.date.available |
2024-02-01T00:37:06Z |
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dc.date.created |
2019-09-25 |
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dc.date.issued |
2019-04-11 |
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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. |
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dc.identifier.bibliographicCitation |
한국구조물진단유지관리공학회 2019년 봄 학술발표회, pp.118 - 119 |
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dc.identifier.uri |
https://scholarworks.unist.ac.kr/handle/201301/80024 |
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dc.language |
한국어 |
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dc.publisher |
한국구조물진단유지관리공학회 |
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dc.title.alternative |
Safety evaluation of nuclear spent-fuel transport casks in puncture events |
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dc.title |
사용후핵연료 운송용기의 관통 안전성 평가 |
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dc.type |
Conference Paper |
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dc.date.conferenceDate |
2019-04-10 |
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