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dc.contributor.authorKleingeld, Marius
dc.contributor.authorJanse van Rensburg, Jacobus Johannes
dc.date.accessioned2012-11-15T06:16:48Z
dc.date.available2012-11-15T06:16:48Z
dc.date.issued2011
dc.identifier.citationJanse van Rensburg, J.J. & Kleingeld, M. 2011. Investigating leakage and bypass flows in an HTR using a CFD methodology. Nuclear engineering and design, 241(12):4960-4971. [http://www.journals.elsevier.com/nuclear-engineering-and-design/]en_US
dc.identifier.issn0029-5493
dc.identifier.issn1872-759X (Online)
dc.identifier.urihttp://hdl.handle.net/10394/7762
dc.description.abstractAn area that has been identified as significantly important in the development of a high temperature reactor (HTR) is the prediction of leakage and bypass flows. It is therefore essential to understand the influence of leakage and bypass flows on the thermal performance of an HTR. A methodology was developed to conduct an integral thermal analysis of a reactor using a CFD approach. One of the main objectives was to include leakage and bypass flow paths in order to provide a capability for simulating these very detailed flows. This paper investigates leakage and bypass flows through the PBMR reactor unit. It was found that, although these flows are dependent on the pressure drop through the pebble bed, a change in pebble bed pressure drop does not result in a similar change in the predicted leakages flows. It is also shown that the ability to account for leakage and bypass flows in an integral manner can help designers to focus their efforts on the specific regions that need to be targeted for the improvement of the life expectancy of the graphite blocks. Furthermore, leakage and bypass flows were found to reduce the pressure drop across the reactor unit while increasing the peak fuel temperatures.en_US
dc.description.urihttp://dx.doi.org/10.1016/j.nucengdes.2011.08.073
dc.language.isoenen_US
dc.publisherElsevieren_US
dc.subjectCFDen_US
dc.subjectleakage flowsen_US
dc.subjectbypass flowsen_US
dc.subjectPBMRen_US
dc.subjectreactor flow distributionen_US
dc.subjecthigh temperature reactoren_US
dc.titleInvestigating leakage and bypass flows in an HTR using a CFD methodologyen_US
dc.typeArticleen_US


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