Multiregion Analysis of Conduction and Convective Heat Transfer in a Finite Tube Bundle Reactor (Rod Bundle)
Kar, Aravinda
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https://hdl.handle.net/2142/70905
Description
Title
Multiregion Analysis of Conduction and Convective Heat Transfer in a Finite Tube Bundle Reactor (Rod Bundle)
Author(s)
Kar, Aravinda
Issue Date
1986
Department of Study
Nuclear Engineering
Discipline
Nuclear Engineering
Degree Granting Institution
University of Illinois at Urbana-Champaign
Degree Name
Ph.D.
Degree Level
Dissertation
Keyword(s)
Engineering, Nuclear
Abstract
A theoretical investigation has been carried out to determine the temperature fields and the heat transfer rates in various regions of a rod-clustered circular channel. Analytical results for two cases, the thermal entrance region and the thermally developed region, have been presented. In the thermally developed region the continuity of temperature and the heat flux at the interfaces have been considered, and the analysis has been extended to both plug and fully developed laminar flow. The singular solution arising due to the peripheral rods has been obtained using the method of Howland functions.
Also, an approximate expression for the developed laminar flow has been determined using the method of weighted residuals, and its accuracy has been examined analytically. In the entrance region the longitudinal development of the coolant temperature has been studied using the above method. Finally, a criterion for the choice of trial function for the method of weighted residuals has been presented.
The advantage of being able to carry out an extensive parametric survey at a low computational cost on the basis of the analytic solutions obtained in this study is demonstrated.
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