Full Text Available

Note: Clicking the button above will open the full text document at the original institutional repository in a new window.

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

Dissertation (MSc)--University of Pretoria, 2019.

Saved in:
Bibliographic Details
Other Authors: Slabber, Johan F.M.
Format: Thesis
Language:English
Published: University of Pretoria 2019
Subjects:
Tags: Add Tag
No Tags, Be the first to tag this record!
_version_ 1867613568227082240
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