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Investigating leakage and bypass flows in an HTR using a CFD methodology

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dc.contributor.author Kleingeld, Marius
dc.contributor.author Janse van Rensburg, Jacobus Johannes
dc.date.accessioned 2012-11-15T06:16:48Z
dc.date.available 2012-11-15T06:16:48Z
dc.date.issued 2011
dc.identifier.citation Janse 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.issn 0029-5493
dc.identifier.issn 1872-759X (Online)
dc.identifier.uri http://hdl.handle.net/10394/7762
dc.description.abstract An 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.uri http://dx.doi.org/10.1016/j.nucengdes.2011.08.073
dc.language.iso en en_US
dc.publisher Elsevier en_US
dc.subject CFD en_US
dc.subject leakage flows en_US
dc.subject bypass flows en_US
dc.subject PBMR en_US
dc.subject reactor flow distribution en_US
dc.subject high temperature reactor en_US
dc.title Investigating leakage and bypass flows in an HTR using a CFD methodology en_US
dc.type Article en_US


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