• Title of article

    Investigating effects of BCC and FCC arrangements on flow and heat transfer characteristics in pebbles through CFD methodology

  • Author/Authors

    Ferng، نويسنده , , Yuh Ming and Lin، نويسنده , , Kun-Yueh Lin، نويسنده ,

  • Issue Information
    روزنامه با شماره پیاپی سال 2013
  • Pages
    10
  • From page
    66
  • To page
    75
  • Abstract
    A high temperature gas cooled reactor (HTGR) would be one of the possible energy generation sources due to its advantages of inherently safety performance and higher conversion efficiency, etc. However, safety is the most important issue for its commercialization in energy industry. It is very crucial for safety design and operation of an HTGR to investigate its thermal–hydraulic characteristics. In this article, a computational fluid dynamics (CFD) methodology is proposed to investigate effects of different arrangements on these characteristics for an HTGR with a pebble bed (PB) core. Two kinds of arrangement: body-centered cubic (BCC) and face-centered cubic (FCC) are studies herein. Based on the simulation results, higher heat transfer capability and lower pebble temperature are predicted in the pebbles with the FCC-arrangement. The thermally fully-developed flow condition may be reached, which is shown in the result that the predicted average Nussel (Nu) number decreases from the 1st layer and reaches to an asymptotic value as the gas passes through the 6th layer of pebbles. This entrance effect reveals that the system codes using the correlations developed from the fully-developed flow condition can be appropriately applied in the entire PBR core. In addition, the present predicted dependence of Nu number on the inlet Reynolds (Re) number shows good agreement with that obtained from the well-known KTA. Measured data of Nu number versus Re number are also used to validate the CFD model.
  • Keywords
    HTGR , CFD methodology non-uniform heat transfer on pebbles , FCC and BCC in pebble bed
  • Journal title
    Nuclear Engineering and Design Eslah
  • Serial Year
    2013
  • Journal title
    Nuclear Engineering and Design Eslah
  • Record number

    1593255