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FynanDouglas

Fynan, Douglas A.
Nuclear Science, Simulation & Safety Lab.
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dc.citation.endPage 701 -
dc.citation.number 3 -
dc.citation.startPage 684 -
dc.citation.title NUCLEAR ENGINEERING AND TECHNOLOGY -
dc.citation.volume 48 -
dc.contributor.author Fynan, Douglas A. -
dc.contributor.author Ahn, Kwang-Il -
dc.date.accessioned 2023-12-21T23:38:44Z -
dc.date.available 2023-12-21T23:38:44Z -
dc.date.created 2018-08-29 -
dc.date.issued 2016-06 -
dc.description.abstract The Gaussian process model (GPM) is a flexible surrogate model that can be used for nonparametric regression for multivariate problems. A unique feature of the GPM is that a prediction variance is automatically provided with the regression function. In this paper, we estimate the safety margin of a nuclear power plant by performing regression on the output of best-estimate simulations of a large-break loss-of-coolant accident with sampling of safety system configuration, sequence timing, technical specifications, and thermal hydraulic parameter uncertainties. The key aspect of our approach is that the GPM regression is only performed on the dominant input variables, the safety injection flow rate and the delay time for AC powered pumps to start representing sequence timing uncertainty, providing a predictive model for the peak clad temperature during a reflood phase. Other uncertainties are interpreted as contributors to the measurement noise of the code output and are implicitly treated in the GPM in the noise variance term, providing local uncertainty bounds for the peak clad temperature. We discuss the applicability of the foregoing method to reduce the use of conservative assumptions in best estimate plus uncertainty (BEPU) and Level 1 probabilistic safety assessment (PSA) success criteria definitions while dealing with a large number of uncertainties. -
dc.identifier.bibliographicCitation NUCLEAR ENGINEERING AND TECHNOLOGY, v.48, no.3, pp.684 - 701 -
dc.identifier.doi 10.1016/j.net.2016.01.016 -
dc.identifier.issn 1738-5733 -
dc.identifier.scopusid 2-s2.0-84973293265 -
dc.identifier.uri https://scholarworks.unist.ac.kr/handle/201301/24698 -
dc.identifier.wosid 000377974800010 -
dc.language 영어 -
dc.publisher KOREAN NUCLEAR SOC -
dc.title Implicit Treatment of Technical Specification and Thermal Hydraulic Parameter Uncertainties in Gaussian Process Model to Estimate Safety Margin -
dc.type Article -
dc.description.journalRegisteredClass scie -
dc.description.journalRegisteredClass scopus -
dc.description.journalRegisteredClass kci -
dc.subject.keywordAuthor Gaussian Process Model -
dc.subject.keywordAuthor Large-Break Loss-of-Coolant Accident (LBLOCA) -
dc.subject.keywordAuthor Success Criteria -
dc.subject.keywordAuthor Safety Margin -

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