Correlations for some Thermal Hydraulic Parameters for a Pressurized Water Reactor

著者

  • Beinmotei Kenoll Orumo University of Port Harcourt image/svg+xml
  • Abarasi Hart
  • Ayoade Kuye

要旨

 Pressurized Water Reactor (PWR) constitutes majority of nuclear power plants used worldwide because of its stability which enhances operability.  However, the design and safe operation of the PWR is dependent on certain thermal hydraulic parameters such as friction factor and heat transfer. In this study, therefore the correlations for the calculation of the two important thermal hydraulic parameters are presented. Correlations used include: Dittus-Boelter and Chilton-Colburn for heat transfer, Blasius and Drew et al. for the friction factor. Microsoft Excel regression analysis and the solver tools were used to determine the various parameters for these correlations. The correlations are applicable within the range 2000 < Re < 5×106 and 0.5 < Pr < 2000 for the heat transfer and 3000 ≤ Re ≤ 3×105 for the friction factor. Experimental data obtained from literature were then used to validate the different correlation parameters. It was found that the lowest average and maximum percentage deviations for friction factor are: Blasius (0.38% and 0.74%) and Drew et al. (0.62% and 1.48%). For the heat transfer: Dittus-Boelter (less than 0.01%) and Chilton-Colburn (0.31% and 0.85%). Keywords: Friction factor, Heat transfer, Thermal hydraulic 

著者略歴

  • Beinmotei Kenoll Orumo、 University of Port Harcourt
    Nuclear Power Plant Development Derectoriate

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発行日

2016-01-19

巻号

巻 6 号 1 (2016)

セクション

Research Papers

ライセンス

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