{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/85912"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/85912","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"Combined Modeling and Experimental Validation of Boiling Curve and Critical Heat Flux","abstract":"To verify this model, experiments are conducted for a range of conditions. A highspeed, high-fidelity imaging system is employed to quantitatively investigate the bubble motion. Predictions are compared with experimental measurements in this study as well as data available in the literature, with an overall good agreement achieved. An average error of +/-25% is observed for the boiling curve prediction, while for the critical heat flux the prediction error is limited within +/-20%, which equals or supersedes most available semi-empirical models or correlations. This model captures and correctly describes the stochastic nature of the flow and thermal variations, as well as the tightly coupled bubble motion in the flow and thermal fields. This suggests that to extend the modeling of subcooled nucleate boiling to predict critical heat flux, both probabilistic formulation and stochastic analysis need to be utilized.","abstract_html":"To verify this model, experiments are conducted for a range of conditions. A highspeed, high-fidelity imaging system is employed to quantitatively investigate the bubble motion. Predictions are compared with experimental measurements in this study as well as data available in the literature, with an overall good agreement achieved. An average error of +/-25% is observed for the boiling curve prediction, while for the critical heat flux the prediction error is limited within +/-20%, which equals or supersedes most available semi-empirical models or correlations. This model captures and correctly describes the stochastic nature of the flow and thermal variations, as well as the tightly coupled bubble motion in the flow and thermal fields. This suggests that to extend the modeling of subcooled nucleate boiling to predict critical heat flux, both probabilistic formulation and stochastic analysis need to be utilized.","abstract_has_math":false,"creators":["Wu, Wen"],"institution":"University of Illinois at Urbana-Champaign","degree_name":"Ph.D.","degree_level":"Dissertation","degree_discipline":"Nuclear Engineering","degree_department":null,"school":null,"contributors":["Jones, Barclay G.","Newell, Ty A."],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2015,"date_issued":"2015-09-28T14:51:06Z","date_published":"2015-09-28T14:51:06Z","updated_at":"2026-07-22T22:26:26Z","subjects":["Engineering, Mechanical"],"languages":["eng"],"rights":[],"rights_urls":[],"identifier_entries":[{"key":"dc:identifier","label":"Identifier","values":["(MiAaPQ)AAI3270054"],"render_values":[{"text":"(MiAaPQ)AAI3270054","href":null,"code":true}]}]},"links":{"outbound_url":"http://hdl.handle.net/2142/85912","outbound_label":"Handle","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Jones, Barclay G.","Newell, Ty A."]},{"key":"dc:creator","label":"Author","values":["Wu, Wen"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2015-09-28T14:51:06Z","10000-01-01","2007"]},{"key":"dc:type","label":"Dc Type","values":["text"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear Engineering"]},{"key":"thesis:degree_level","label":"Degree Level","values":["Dissertation"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph.D."]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["University of Illinois at Urbana-Champaign"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Engineering, Mechanical"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["eng"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["http://hdl.handle.net/2142/85912","(MiAaPQ)AAI3270054"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["To verify this model, experiments are conducted for a range of conditions. 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No. of bitstreams: 2 license.txt: 4848 bytes, checksum: 96035ab3f5e1c23cc7138a224ce498bd (MD5) 3270054.pdf: 3424822 bytes, checksum: e297f4880576a42bacebaab6f7d1372a (MD5) Previous issue date: 2007","Embargo set by: Seth Robbins for item 87193 Lift date: Forever Reason: Restricted to the U of I community idenfinitely during batch ingest of legacy ETDs","Restricted to the U of I community idenfinitely during batch ingest of legacy ETDs","U of I Only","145 p.","Thesis (Ph.D.)--University of Illinois at Urbana-Champaign, 2007."],"dc:identifier":["http://hdl.handle.net/2142/85912","(MiAaPQ)AAI3270054"],"dc:language":["eng"],"dc:subject":["Engineering, Mechanical"],"dc:title":["Combined Modeling and Experimental Validation of Boiling Curve and Critical Heat Flux"],"dc:type":["text"],"thesis:degree_discipline":["Nuclear Engineering"],"thesis:degree_level":["Dissertation"],"thesis:degree_name":["Ph.D."],"thesis:institution_name":["University of Illinois at Urbana-Champaign"]},"updated_at":"2026-07-22T22:26:26Z"}