dc.citation.conferencePlace |
US |
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dc.citation.endPage |
111 |
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dc.citation.startPage |
106 |
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dc.citation.title |
16th International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2019 |
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dc.contributor.author |
Fynan, Douglas A. |
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dc.contributor.author |
Park, J |
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dc.date.accessioned |
2024-02-01T00:36:01Z |
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dc.date.available |
2024-02-01T00:36:01Z |
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dc.date.created |
2020-02-20 |
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dc.date.issued |
2019-04-28 |
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dc.description.abstract |
The study investigates the degradation of the heat transfer performance of a closed-circuit intermediate natural circulation heat transport loop used as a passive safety system in a nuclear power plant (NPP). Several operator actions related to a feed and bleed emergency operating procedure (F&B) are postulated, and system TH code simulations are performed to demonstrate how the F&B can induce two-phase flow conditions in the RCS. The two-phase flow regimes in RCS hot leg can significantly reduce the heat transfer to the circulating working fluid of the interfacing heat transport loop over long periods, sometimes lasting over 24 hours, of passive system mission time. A transient performance indicator for the passive system mission is introduced for use in passive reliability assessment and quantitative comparison of transient simulations. The need to consider human factors in the design and operation of NPP passive safety systems is stressed. |
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dc.identifier.bibliographicCitation |
16th International Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2019, pp.106 - 111 |
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dc.identifier.issn |
0000-0000 |
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dc.identifier.scopusid |
2-s2.0-85067122166 |
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dc.identifier.uri |
https://scholarworks.unist.ac.kr/handle/201301/79882 |
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dc.language |
영어 |
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dc.publisher |
American Nuclear Society |
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dc.title |
Interfacing passive system performance degradation initiated by nuclear power plant operator action |
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dc.type |
Conference Paper |
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dc.date.conferenceDate |
2019-04-28 |
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