Use this URL to cite or link to this record in EThOS: http://ethos.bl.uk/OrderDetails.do?uin=uk.bl.ethos.470519
Title: The critical heat flux under pool boiling and confined boiling conditions
Author: Riley, James A.
Awarding Body: University of Glasgow
Current Institution: University of Glasgow
Date of Award: 1973
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Abstract:
This thesis contains an account of research work carried out by the author at the Scottish Universities Research and Reactor Centre at East Kilbride, Scotland. The subject of the research was an investigation into the critical or limiting heat flux phenomenon under pool boiling; and confined boiling conditions. This phenomenon is of interest in the field of Nuclear Reactor Technology because it is a phenomenon that can limit the maximum power output of liquid cooled nuclear reactors. The research reported is divided into two sections, Part I dealing with the critical heat flux phenomenon for horizontally mounted heater specimen under pool boiling conditions and Part II dealing with the critical or limiting heat flux phenomenon for vertically mounted specimen under pool boiling and confined boiling conditions. In Part I both the rig and the heater assemblies were designed and commissioned by the author who also built the rig with Technician and Workshop assistance. The rig was operated by the author with Technician assistance and the experimental results were obtained by the author. The analysis, discussion and presentation of the results in Part I is due to the author and where these results are compared to other researchers work due recognition is given by an appropriate reference to the researcher involved. In Part II the rig and annuli heater assemblies were designed and commissioned by the author. The rig was also built by the author with Technician assistance. All the experimental results reported were obtained by the author with Technician assistance. Analysis, discussion and presentation of the results is due to the author. The theory developed in this part of the thesis is also mainly due to the author and where the author has drawn on the work of others this has been duly acknowledged in the text. The results of the horizontal pool boiling investigation reported in Part I tend to support the critical heat flux model due to Zuber (17,18) and to show that this model is still applicable to results obtained under vacuum conditions. HowThis thesis contains an account of research work carried out by the author at the Scottish Universities Research and Reactor Centre at East Kilbride, Scotland. The subject of the research was an investigation into the critical or limiting heat flux phenomenon under pool boiling; and confined boiling conditions. This phenomenon is of interest in the field of Nuclear Reactor Technology because it is a phenomenon that can limit the maximum power output of liquid cooled nuclear reactors. The research reported is divided into two sections, Part I dealing with the critical heat flux phenomenon for horizontally mounted heater specimen under pool boiling conditions and Part II dealing with the critical or limiting heat flux phenomenon for vertically mounted specimen under pool boiling and confined boiling conditions. In Part I both the rig and the heater assemblies were designed and commissioned by the author who also built the rig with Technician and Workshop assistance. The rig was operated by the author with Technician assistance and the experimental results were obtained by the author. The analysis, discussion and presentation of the results in Part I is due to the author and where these results are compared to other researchers work due recognition is given by an appropriate reference to the researcher involved. In Part II the rig and annuli heater assemblies were designed and commissioned by the author. The rig was also built by the author with Technician assistance. All the experimental results reported were obtained by the author with Technician assistance. Analysis, discussion and presentation of the results is due to the author. The theory developed in this part of the thesis is also mainly due to the author and where the author has drawn on the work of others this has been duly acknowledged in the text. The results of the horizontal pool boiling investigation reported in Part I tend to support the critical heat flux model due to Zuber (17,18) and to show that this model is still applicable to results obtained under vacuum conditions. HowThis thesis contains an account of research work carried out by the author at the Scottish Universities Research and Reactor Centre at East Kilbride, Scotland. The subject of the research was an investigation into the critical or limiting heat flux phenomenon under pool boiling; and confined boiling conditions. This phenomenon is of interest in the field of Nuclear Reactor Technology because it is a phenomenon that can limit the maximum power output of liquid cooled nuclear reactors. The research reported is divided into two sections, Part I dealing with the critical heat flux phenomenon for horizontally mounted heater specimen under pool boiling conditions and Part II dealing with the critical or limiting heat flux phenomenon for vertically mounted specimen under pool boiling and confined boiling conditions. In Part I both the rig and the heater assemblies were designed and commissioned by the author who also built the rig with Technician and Workshop assistance. The rig was operated by the author with Technician assistance and the experimental results were obtained by the author. The analysis, discussion and presentation of the results in Part I is due to the author and where these results are compared to other researchers work due recognition is given by an appropriate reference to the researcher involved. In Part II the rig and annuli heater assemblies were designed and commissioned by the author. The rig was also built by the author with Technician assistance. All the experimental results reported were obtained by the author with Technician assistance. Analysis, discussion and presentation of the results is due to the author. The theory developed in this part of the thesis is also mainly due to the author and where the author has drawn on the work of others this has been duly acknowledged in the text. The results of the horizontal pool boiling investigation reported in Part I tend to support the critical heat flux model due to Zuber (17,18) and to show that this model is still applicable to results obtained under vacuum conditions. However the results also show some limitations to this 'hydrodynamic' model in the sense that reduced heat fluxes were obtained as the heater tube wall thickness was reduced and also for heaters with contaminated surfaces. Neither of these effects are predicted by the Zuber model although the recent approach to this problem due to Ouwerkerk (13) could form a basis for taking account of the wall thickness effect. The results of the vertical heater-annular geometry investigation reported in Part II of this thesis have been successfully correlated and compared with the predictions of the theoretical model developed. Both the results for saturated liquid entry and for subcooled liquid entry to the annulus have been found to be compatible with the theoretical model predictions.
Supervisor: Not available Sponsor: Not available
Qualification Name: Thesis (Ph.D.) Qualification Level: Doctoral
EThOS ID: uk.bl.ethos.470519  DOI: Not available
Keywords: TK Electrical engineering. Electronics Nuclear engineering
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