2013
DOI: 10.1080/00223131.2014.866057
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Quantitative common cause failure modeling for auxiliary feedwater system involving the seismic-induced degradation of flood barriers

Abstract: Flood barriers are important defenses which will reduce the internal flood-induced failure risk of safetyrelated equipment in the turbine building. Contrarily, the degradation of flood barriers will increase the risk of internal flood-induced common cause failure (CCF). Two layouts of auxiliary feedwater pumps system are compared to demonstrate the quantitative risk assessment of the possible degradation of flood barriers. The alpha decomposition method has been developed by the authors in order to quantitativ… Show more

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Cited by 5 publications
(2 citation statements)
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“…The auxiliary feedwater electric pump, serving as a backup in the event of a nuclear main pump failure, plays a critical role in dissipating residual heat from the core during main water supply system malfunctions [1,2]. As a pivotal component in the energy system, this pump demands exceptional vibration performance and seismic reliability.…”
Section: Introductionmentioning
confidence: 99%
“…The auxiliary feedwater electric pump, serving as a backup in the event of a nuclear main pump failure, plays a critical role in dissipating residual heat from the core during main water supply system malfunctions [1,2]. As a pivotal component in the energy system, this pump demands exceptional vibration performance and seismic reliability.…”
Section: Introductionmentioning
confidence: 99%
“…Researchers have aimed to overcome this limitation using dynamic PRA. For example, Zheng et al 4 and Jang et al 5 analyzed the relationship between room layout and the time it took for the water level to rise in each room and evaluated the time dependency of conditional core damage probability (CCDP) during seismic-induced internal flooding. Mandelli et al 6 conducted a detailed risk assessment by coupling computational fluid dynamics software, NEUTRINO, 7 and thermalhydraulic analysis using RELAP (Reactor Excursion and Leak Analysis Program) 8 and RAVEN (Reactor Analysis and Virtual Control Environment).…”
Section: Introductionmentioning
confidence: 99%