Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations
In a worldwide pursuit for more Accident Tolerant nuclear Fuel (ATF), the quest to obtain and certify alternative nuclear fuel cladding tubes for light-water nuclear power reactors is still a key challenge. One of the facets in this program to develop more ATF is the heat transfer evaluation between...
id |
ndltd-netd.ac.za-oai-union.ndltd.org-up-oai-repository.up.ac.za-2263-71554 |
---|---|
record_format |
oai_dc |
spelling |
ndltd-netd.ac.za-oai-union.ndltd.org-up-oai-repository.up.ac.za-2263-715542021-03-26T05:11:07Z Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations Govinder, Kuvendran Slabber, Johan F.M. chris.govinder@up.ac.za Meyer, Josua P. External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD In a worldwide pursuit for more Accident Tolerant nuclear Fuel (ATF), the quest to obtain and certify alternative nuclear fuel cladding tubes for light-water nuclear power reactors is still a key challenge. One of the facets in this program to develop more ATF is the heat transfer evaluation between the various proposed clad tubes manufactured from suitable replacement materials and the current problematic zirconium-alloy based clad tubes used in nuclear power reactors. For the heat transfer analysis, the accurate measurement of the temperature on the heat transfer surface of heated tubes to be tested was one of the important objectives for the effective analysis of the heat transfer characteristics to the water coolant. After extensive investigations, a suitable technique was developed and validated against recognised forced-convection heat transfer correlations. The results showed that this technique was well suited for external forced convection heat transfer studies from heated surfaces exposed to forced convection water coolants. Dissertation (MSc)--University of Pretoria, 2019. Mechanical and Aeronautical Engineering MSc (Applied Science - Mechanics) Unrestricted 2019-10-02T11:20:49Z 2019-10-02T11:20:49Z 2019-08-30 2019 Dissertation http://hdl.handle.net/2263/71554 Govinder, K 2019, Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations, MSc (Applied Science - Mechanics) Dissertation, University of Pretoria, Pretoria, viewed yymmdd <http://hdl.handle.net/2263/71554> A2020 en © 2019 University of Pretoria. All rights reserved. The copyright in this work vests in the University of Pretoria. No part of this work may be reproduced or transmitted in any form or by any means, without the prior written permission of the University of Pretoria. University of Pretoria |
collection |
NDLTD |
language |
en |
sources |
NDLTD |
topic |
External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD |
spellingShingle |
External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD Govinder, Kuvendran Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
description |
In a worldwide pursuit for more Accident Tolerant nuclear Fuel (ATF), the quest to obtain and certify alternative nuclear fuel cladding tubes for light-water nuclear power reactors is still a key challenge. One of the facets in this program to develop more ATF is the heat transfer evaluation between the various proposed clad tubes manufactured from suitable replacement materials and the current problematic zirconium-alloy based clad tubes used in nuclear power reactors. For the heat transfer analysis, the accurate measurement of the temperature on the heat transfer surface of heated tubes to be tested was one of the important objectives for the effective analysis of the heat transfer characteristics to the water coolant. After extensive investigations, a suitable technique was developed and validated against recognised forced-convection heat transfer correlations. The results showed that this technique was well suited for external forced convection heat transfer studies from heated surfaces exposed to forced convection water coolants. === Dissertation (MSc)--University of Pretoria, 2019. === Mechanical and Aeronautical Engineering === MSc (Applied Science - Mechanics) === Unrestricted |
author2 |
Slabber, Johan F.M. |
author_facet |
Slabber, Johan F.M. Govinder, Kuvendran |
author |
Govinder, Kuvendran |
author_sort |
Govinder, Kuvendran |
title |
Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
title_short |
Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
title_full |
Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
title_fullStr |
Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
title_full_unstemmed |
Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
title_sort |
theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations |
publisher |
University of Pretoria |
publishDate |
2019 |
url |
http://hdl.handle.net/2263/71554 Govinder, K 2019, Theoretical analyses and design, construction and testing of a flow loop for the study of generalised forced and natural convection boiling heat transfer phenomena on typical light-water nuclear reactor fuel pin configurations, MSc (Applied Science - Mechanics) Dissertation, University of Pretoria, Pretoria, viewed yymmdd <http://hdl.handle.net/2263/71554> |
work_keys_str_mv |
AT govinderkuvendran theoreticalanalysesanddesignconstructionandtestingofaflowloopforthestudyofgeneralisedforcedandnaturalconvectionboilingheattransferphenomenaontypicallightwaternuclearreactorfuelpinconfigurations |
_version_ |
1719384598037659648 |