日本原子力学会 年会・大会予稿集
2008 Fall Meeting
セッションID: E37
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数値解析
Comparative Study of Turbulence Models on PWR Fuel Bundle Thermal Hydraulics Using FLUENT Code
*Endiah Puji HASTUTIAkira YAMAGUCHITakashi TAKATA
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会議録・要旨集 フリー

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抄録
To understand the turbulence heat and mass transfer in PWR 17x17 fuel bundle, FLUENT analyses are performed. The objective of this paper is to present the results of sensitivity analysis by comparing of turbulence models. Three turbulence models have been used for the CFD calculations with a systematic refinement of the mesh at least in two steps.
著者関連情報
© 2008 Atomic Energy Society of Japan
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