CFD Analysis of Localised Crud Effects on the Flow of Coolant in Nuclear Rod Bundles
File(s)NEDPaper.Revised.pdf (14.09 MB)
Accepted version
Author(s)
Cinosi, N
Walker, SP
Type
Journal Article
Abstract
It has been suggested that crud deposits on a number of adjacent fuel rods might
reduce coolant flow rates in associated sub-channels. Such reduced flow rates could
then worsen thermal-hydraulic conditions, such as margin to saturated boiling, fuel
surface temperature, and the DNB ratio. We report the results of a detailed
computational fluid dynamics study of the flow pattern in a partially-crudded rod
bundle. Values obviously depend on, for example, the thickness of crud assumed,
but sub-channel flow rate reductions of ~10% were predicted by this analysis.
However, this mass flow rate reduction was found to be more than offset by
improved heat transfer induced by the relatively rough surface of the crud. Cladding
temperatures were predicted to be essentially unchanged, and the DNBR was
similarly little altered. We conclude that such flow reduction and diversion is not likely
to be of concern.
reduce coolant flow rates in associated sub-channels. Such reduced flow rates could
then worsen thermal-hydraulic conditions, such as margin to saturated boiling, fuel
surface temperature, and the DNB ratio. We report the results of a detailed
computational fluid dynamics study of the flow pattern in a partially-crudded rod
bundle. Values obviously depend on, for example, the thickness of crud assumed,
but sub-channel flow rate reductions of ~10% were predicted by this analysis.
However, this mass flow rate reduction was found to be more than offset by
improved heat transfer induced by the relatively rough surface of the crud. Cladding
temperatures were predicted to be essentially unchanged, and the DNBR was
similarly little altered. We conclude that such flow reduction and diversion is not likely
to be of concern.
Date Issued
2016-06-02
Date Acceptance
2015-12-07
Citation
Nuclear Engineering and Design, 2016, 305, pp.28-38
ISSN
0029-5493
Publisher
Elsevier
Start Page
28
End Page
38
Journal / Book Title
Nuclear Engineering and Design
Volume
305
Copyright Statement
© 2016, Elsevier. Licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 4.0 International http://creativecommons.org/licenses/by-nc-nd/4.0/
Sponsor
Engineering & Physical Science Research Council (EPSRC)
Engineering & Physical Science Research Council (EPSRC)
Grant Number
EP/I003010/1
EP/I012427/1
Subjects
Energy
0915 Interdisciplinary Engineering
Publication Status
Published