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Dissertation (MSc)--University of Pretoria, 2019.
| Other Authors: | |
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| Format: | Thesis |
| Language: | English |
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University of Pretoria
2019
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| _version_ | 1867613568227082240 |
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| access_status_str | Open Access |
| author2 | Slabber, Johan F.M. |
| author_browse | Slabber, Johan F.M. |
| author_facet | Slabber, Johan F.M. |
| collection | Thesis |
| dc_rights_str_mv | © 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. |
| description | Dissertation (MSc)--University of Pretoria, 2019. |
| format | Thesis |
| id | oai:repository.up.ac.za:2263/71554 |
| institution | University of Pretoria (South Africa) |
| language | English |
| last_indexed | 2026-06-10T12:38:12.930Z |
| license_str | Other — see source repository |
| provenance_str_mv | Harvested via OAI-PMH from UPSpace — University of Pretoria Institutional Repository |
| publishDate | 2019 |
| publishDateRange | 2019 |
| publishDateSort | 2019 |
| publisher | University of Pretoria |
| publisherStr | University of Pretoria |
| record_format | dspace |
| source_str | UPSpace — University of Pretoria Institutional Repository |
| spelling | oai:repository.up.ac.za:2263/71554 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 Slabber, Johan F.M. chris.govinder@up.ac.za Meyer, Josua P. Govinder, Kuvendran External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD Engineering, built environment and information technology theses SDG-07 SDG-07: Affordable and clean energy Engineering, built environment and information technology theses SDG-09 SDG-09: Industry, innovation and infrastructure Engineering, built environment and information technology theses SDG-13 SDG-13: Climate action Dissertation (MSc)--University of Pretoria, 2019. 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. mi2025 Mechanical and Aeronautical Engineering MSc (Applied Science - Mechanics) Unrestricted SDG-07: Affordable and clean energy SDG-09: Industry, innovation and infrastructure SDG-13: Climate action 2019-10-02T11:20:49Z 2019-10-02T11:20:49Z 2019-08-30 2019 Dissertation 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 http://hdl.handle.net/2263/71554 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. application/pdf University of Pretoria |
| spellingShingle | External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD Engineering, built environment and information technology theses SDG-07 SDG-07: Affordable and clean energy Engineering, built environment and information technology theses SDG-09 SDG-09: Industry, innovation and infrastructure Engineering, built environment and information technology theses SDG-13 SDG-13: Climate action 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 | 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_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_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 |
| topic | External flow boiling Fuel clad-tubes Silicon Carbide Accident Tolerant Fuel for Light Water Nuclear Reactors Surface temperature measurement UCTD Engineering, built environment and information technology theses SDG-07 SDG-07: Affordable and clean energy Engineering, built environment and information technology theses SDG-09 SDG-09: Industry, innovation and infrastructure Engineering, built environment and information technology theses SDG-13 SDG-13: Climate action |
| url | http://hdl.handle.net/2263/71554 |