Thermal Analysis of A Pebble Bed High Temperature Gas Cooled Reactor
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University of Ghana
Abstract
The pebble bed type of high temperature gas cooled nuclear reactor is a promising
option for next generation reactor technology and has the potential to provide high
efficiency and cost effective electricity generation. The reactor unit heat transfer
poses a challenge due to the complexity associated with it. In the pebble bed, heat
is generated in kernels inside the fuel sphere. The generated heat is conducted to
the sphere surface where it is transferred to the coolant (helium gas) by means of
convection. In the bed itself when a temperature gradient exists across the bed,
heat is transferred between pebbles by means of conduction and interstitial
radiation in the radial and axial directions. This necessitates a heat transfer model
that deals with radiation as well as thermal convection and conduction. Modeling
such a complex thermal hydraulic system requires the use of variety of techniques
and simulation tools ranging from a one-dimensional model to large scale three dimensional
model using computer codes based on analytical or computational
fluid dynamics. In this research, a simplified analytical model of the pebble bed
type high temperature nuclear reactor heat transfer was developed to analyze the
convection, conduction and radiation heat transfer phenomena, as well as the loss
of pressure through friction in the pebble bed. Correlations derived from
experimental data or directly from experimental testing were used to approximate
the thermo-physical properties of the pebble bed. The developed model was
implemented on a personal computer using a simulation code PEBTAN (PEbble
Bed Thermal Analysis code) which was written in FORTRAN 95 programming
language. Simulation and numerical experiments were conducted, and the results
showed very good agreement with published data. The model can adequately
account for the heat transfer phenomenon, and the loss of pressure through
friction in the pebble bed type high temperature nuclear reactor. The model can
serve as the bases for a more detailed three dimensional computational fluid
dynamic analysis.
Description
Thesis (MPhil) - University of Ghana, 2009