Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
Online ISSN : 2424-2934
セッションID: ICONE19-43900
会議情報
ICONE19-43900 PREDICTION OF BYPASS FLOWS IN HTR-PM BY THE FLOW NETWORK METHOD
Jun SunYanhua ZhengFu LiZhe SuiYuanle Ma
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会議録・要旨集 フリー

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抄録
The high temperature gas-cooled reactor is moderated by many graphite bricks. Gaps between graphite reflectors are possible flow paths that some fraction of cold helium may directly enter the hot plenum without being heated, which is a kind of bypass flow. The ratio of the bypass flows to the total flow is a key factor related to the peak fuel temperature in the normal operation of the reactor. Gaps are widely distributed in three dimensional structures, thus building proper flow network is the practical means to describe all the main flow and bypass flow paths by assigning proper nodes and links of the flow network. Graphically illustrated in the Vpower simulator platform, a preliminary flow network was built for the main flow and bypass flow paths. As the resistance performances of all flow paths determined by empirical formulas or CFD tools, the flow network was solved to show the effects of total mass flow rate, outlet pressure as well as the gap size on the mass flow distributions.
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© 2011 一般社団法人 日本機械学会
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