CFD simulations of the spent fuel pool in the loss of coolant accident

dc.contributor.authorLin, Y.T.
dc.contributor.authorChiu, P.H.
dc.contributor.authorChen, B.Y.
dc.contributor.authorChang, C.J.
dc.contributor.authorChan, Y.K.
dc.date.accessioned2014-12-09T11:40:21Z
dc.date.available2014-12-09T11:40:21Z
dc.date.issued2012
dc.description.abstractPaper presented at the 9th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Malta, 16-18 July, 2012.en_US
dc.description.abstractThe study utilized the computational fluid dynamics (CFD) methodology to investigate the thermal hydraulic behavior during the hypothetical event of normal operation and loss of cooling accident occurring at spent fuel pool. The boiling time, water level decreasing rate, fuel exposure time and temperature response after fuel exposure for the nuclear power plants under the accident were predicted in this study. We also analyze the flow and heat transfer for the single Atrium-10 fuel bundle. The details of the physics will be shown in this study. The results indicate that the fuel temperature in the pool will not exceed 1200°C to avoid the water-metal reaction after failure of RHR system for 4.578 days. We find that the velocity in the bundle are much faster than outside of the bundle under the LOCA accident.en_US
dc.description.librariandc2014en_US
dc.format.extent6 pagesen_US
dc.format.mediumPDFen_US
dc.identifier.citationLin, YT, Chiu, PH, Chen, BY, Chang, CJ & Chan, YK 2012, CFD simulations of the spent fuel pool in the loss of coolant accident, Paper presented to the 9th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Malta, 16-18 July, 2012.en_US
dc.identifier.isbn9781868549863
dc.identifier.urihttp://hdl.handle.net/2263/42876
dc.language.isoenen_US
dc.publisherInternational Conference on Heat Transfer, Fluid Mechanics and Thermodynamicsen_US
dc.relation.ispartofHEFAT 2012en_US
dc.rightsUniversity of Pretoriaen_US
dc.subjectComputational fluid dynamicsen_US
dc.subjectCFDen_US
dc.subjectThermal hydraulic behavioren_US
dc.subjectHypothetical eventen_US
dc.subjectAtrium-10 fuel bundleen_US
dc.subjectLOCA accidenten_US
dc.subjectRHR systemen_US
dc.titleCFD simulations of the spent fuel pool in the loss of coolant accidenten_US
dc.typePresentationen_US

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