{"id":{"repo_id":"uoit","oai_identifier":"oai:ontariotechu.scholaris.ca:10155/1202"},"canonical_url":"https://search.dev.ndltd.org/etd/uoit/oai:ontariotechu.scholaris.ca:10155/1202","repository":{"repo_id":"uoit","name":"Ontario Institute of Technology","base_url":"https://ontariotechu.scholaris.ca/server/oai/request"},"display":{"title":"Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water","abstract":"Current Generation II/III/III+ Nuclear Power Plants (NPPs) are no longer economically competitive partially due to low thermal efficiencies. Six Generation IV NPP concepts were proposed having increased thermal efficiency, with Canada investigating the SuperCritical Water Reactor (SCWR) concept. However, determining Heat Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No assessments of Nu correlations are available for 7-rod bundle datasets, representing the centre of 37-element bundles currently used in Canadian NPPs. A Nu correlation derived from a 7-rod bundle dataset is proposed, and assessed against 35 common Nu correlations, using Root Mean Square error and graphical investigation. The assessment indicates the proposed Nu correlation is the most suitable for 7-rod bundles and bare tubes. One typical Canadian SCWR design is confirmed based on maximum fuel centreline and sheath temperatures.","abstract_html":"Current Generation II/III/III+ Nuclear Power Plants (NPPs) are no longer economically competitive partially due to low thermal efficiencies. Six Generation IV NPP concepts were proposed having increased thermal efficiency, with Canada investigating the SuperCritical Water Reactor (SCWR) concept. However, determining Heat Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No assessments of Nu correlations are available for 7-rod bundle datasets, representing the centre of 37-element bundles currently used in Canadian NPPs. A Nu correlation derived from a 7-rod bundle dataset is proposed, and assessed against 35 common Nu correlations, using Root Mean Square error and graphical investigation. The assessment indicates the proposed Nu correlation is the most suitable for 7-rod bundles and bare tubes. One typical Canadian SCWR design is confirmed based on maximum fuel centreline and sheath temperatures.","abstract_has_math":false,"creators":["Clark, Scott E."],"institution":"University of Ontario Institute of Technology","degree_name":"Master of Applied Science (MASc)","degree_level":null,"degree_discipline":"Nuclear Engineering","degree_department":null,"school":null,"contributors":[],"advisors":["Pioro, Igor"],"committee_chairs":[],"committee_members":[],"year":2020,"date_issued":"2020-08-17","date_published":"2020-08-17","updated_at":"2026-07-24T05:35:30Z","subjects":["Heat Transfer Nusselt number Correlation","SuperCritical Water Reactor (SCWR)","Nuclear Engineering","Fuel Bundle","Small Modular Reactor (SMR)"],"languages":["en"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10155/1202","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Pioro, Igor"]},{"key":"dc:creator","label":"Author","values":["Clark, Scott E."]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2021-02-16T17:24:29Z","2022-03-25T18:48:58Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2021-02-16T17:24:29Z","2022-03-25T18:48:58Z"]},{"key":"dc:date.issued","label":"Date","values":["2020-08-17"]},{"key":"dc:type","label":"Dc Type","values":["Thesis"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear Engineering"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Master of Applied Science (MASc)"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["University of Ontario Institute of Technology"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Heat Transfer Nusselt number Correlation","SuperCritical Water Reactor (SCWR)","Nuclear Engineering","Fuel Bundle","Small Modular Reactor (SMR)"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language.iso","label":"Language (ISO)","values":["en"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier.uri","label":"Identifier URI","values":["https://hdl.handle.net/10155/1202"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["Current Generation II/III/III+ Nuclear Power Plants (NPPs) are no longer economically competitive partially due to low thermal efficiencies. Six Generation IV NPP concepts were proposed having increased thermal efficiency, with Canada investigating the SuperCritical Water Reactor (SCWR) concept. However, determining Heat Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No assessments of Nu correlations are available for 7-rod bundle datasets, representing the centre of 37-element bundles currently used in Canadian NPPs. A Nu correlation derived from a 7-rod bundle dataset is proposed, and assessed against 35 common Nu correlations, using Root Mean Square error and graphical investigation. The assessment indicates the proposed Nu correlation is the most suitable for 7-rod bundles and bare tubes. One typical Canadian SCWR design is confirmed based on maximum fuel centreline and sheath temperatures."]},{"key":"dc:title","label":"Title","values":["Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water"]}]}],"canonical_facts":{"dc:contributor.advisor":["Pioro, Igor"],"dc:creator":["Clark, Scott E."],"dc:date.accessioned":["2021-02-16T17:24:29Z","2022-03-25T18:48:58Z"],"dc:date.available":["2021-02-16T17:24:29Z","2022-03-25T18:48:58Z"],"dc:date.issued":["2020-08-17"],"dc:description.abstract":["Current Generation II/III/III+ Nuclear Power Plants (NPPs) are no longer economically competitive partially due to low thermal efficiencies. Six Generation IV NPP concepts were proposed having increased thermal efficiency, with Canada investigating the SuperCritical Water Reactor (SCWR) concept. However, determining Heat Transfer specifics for SuperCritical Water in bundle configurations is required. Many empirical Nusselt number (Nu) correlations derived from bare tubes are available, with only one derived from a bundle. No assessments of Nu correlations are available for 7-rod bundle datasets, representing the centre of 37-element bundles currently used in Canadian NPPs. A Nu correlation derived from a 7-rod bundle dataset is proposed, and assessed against 35 common Nu correlations, using Root Mean Square error and graphical investigation. The assessment indicates the proposed Nu correlation is the most suitable for 7-rod bundles and bare tubes. One typical Canadian SCWR design is confirmed based on maximum fuel centreline and sheath temperatures."],"dc:identifier.uri":["https://hdl.handle.net/10155/1202"],"dc:language.iso":["en"],"dc:subject":["Heat Transfer Nusselt number Correlation","SuperCritical Water Reactor (SCWR)","Nuclear Engineering","Fuel Bundle","Small Modular Reactor (SMR)"],"dc:title":["Specifics of forced-convection heat transfer in a vertical 7-element bundle cooled with upward flow of SuperCritical Water"],"dc:type":["Thesis"],"thesis:degree_discipline":["Nuclear Engineering"],"thesis:degree_name":["Master of Applied Science (MASc)"],"thesis:institution_name":["University of Ontario Institute of Technology"]},"updated_at":"2026-07-24T05:35:30Z"}