ABSTRACT
The Transformational Challenge Reactor (TCR) marks a significant leap forward in nuclear reactor innovation, focusing on modular construction, high efficiency, and improved safety. This research explores the coupled behavior of heat transfer and fluid flow within the TCR's 3D-printed ceramic core under varying operational conditions. Nitrogen was utilized as the cooling medium, with experiments carried out at pressures ranging from 300 to 600 psi and temperatures spanning 100°C to 300°C. Critical parameters, including inlet and outlet gas temperatures, wall temperatures at both ends of the core, and coolant flow rates were monitored to evaluate thermal performance and system reliability. Findings indicate that elevated pressures contribute to better thermal conductivity, while higher flow rates enhance cooling capacity but shorten the coolant’s residence time. The stability of vessel wall temperatures across all test conditions highlights the effectiveness of the system’s insulation. These insights reinforce the TCR’s potential for application in next-generation, high-temperature nuclear systems.
","abstract_html":"<p><strong>ABSTRACT</strong></p> <p>The Transformational Challenge Reactor (TCR) marks a significant leap forward in nuclear reactor innovation, focusing on modular construction, high efficiency, and improved safety. This research explores the coupled behavior of heat transfer and fluid flow within the TCR's 3D-printed ceramic core under varying operational conditions. Nitrogen was utilized as the cooling medium, with experiments carried out at pressures ranging from 300 to 600 psi and temperatures spanning 100°C to 300°C. Critical parameters, including inlet and outlet gas temperatures, wall temperatures at both ends of the core, and coolant flow rates were monitored to evaluate thermal performance and system reliability. Findings indicate that elevated pressures contribute to better thermal conductivity, while higher flow rates enhance cooling capacity but shorten the coolant’s residence time. The stability of vessel wall temperatures across all test conditions highlights the effectiveness of the system’s insulation. These insights reinforce the TCR’s potential for application in next-generation, high-temperature nuclear systems.</p>","abstract_has_math":false,"creators":["Majdoub, EL Mokhtar, EM"],"institution":null,"degree_name":"Master of Engineering (M.E.)","degree_level":"Thesis","degree_discipline":"Mechanical Engineering","degree_department":null,"school":null,"contributors":["Masahiro Kawaji"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2025,"date_issued":"2025-01-01T08:00:00Z","date_published":"2025-01-01T08:00:00Z","updated_at":"2026-07-24T01:58:13Z","subjects":["Master","degree","TCR","Heat","Exchanger","Flow","Engineering"],"languages":[],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://academicworks.cuny.edu/cc_etds_theses/1264","outbound_label":"Repository record","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Masahiro Kawaji"]},{"key":"dc:creator","label":"Author","values":["Majdoub, EL Mokhtar, EM"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.available","label":"Dc Date Available","values":["2025-05-25T07:00:00Z"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Mechanical Engineering"]},{"key":"thesis:degree_level","label":"Degree Level","values":["Thesis"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Master of Engineering (M.E.)"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Master","degree","TCR","Heat","Exchanger","Flow","Engineering"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://academicworks.cuny.edu/cc_etds_theses/1264"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["ABSTRACT
The Transformational Challenge Reactor (TCR) marks a significant leap forward in nuclear reactor innovation, focusing on modular construction, high efficiency, and improved safety. This research explores the coupled behavior of heat transfer and fluid flow within the TCR's 3D-printed ceramic core under varying operational conditions. Nitrogen was utilized as the cooling medium, with experiments carried out at pressures ranging from 300 to 600 psi and temperatures spanning 100°C to 300°C. Critical parameters, including inlet and outlet gas temperatures, wall temperatures at both ends of the core, and coolant flow rates were monitored to evaluate thermal performance and system reliability. Findings indicate that elevated pressures contribute to better thermal conductivity, while higher flow rates enhance cooling capacity but shorten the coolant’s residence time. The stability of vessel wall temperatures across all test conditions highlights the effectiveness of the system’s insulation. These insights reinforce the TCR’s potential for application in next-generation, high-temperature nuclear systems.
"]},{"key":"dc:title","label":"Title","values":["Experimental Characterization of Heat Transfer and Fluid Flow in TCR Fuel Elements under Varying Operational Conditions"]}]}],"canonical_facts":{"dc:contributor":["Masahiro Kawaji"],"dc:creator":["Majdoub, EL Mokhtar, EM"],"dc:date.available":["2025-05-25T07:00:00Z"],"dc:description.abstract":["ABSTRACT
The Transformational Challenge Reactor (TCR) marks a significant leap forward in nuclear reactor innovation, focusing on modular construction, high efficiency, and improved safety. This research explores the coupled behavior of heat transfer and fluid flow within the TCR's 3D-printed ceramic core under varying operational conditions. Nitrogen was utilized as the cooling medium, with experiments carried out at pressures ranging from 300 to 600 psi and temperatures spanning 100°C to 300°C. Critical parameters, including inlet and outlet gas temperatures, wall temperatures at both ends of the core, and coolant flow rates were monitored to evaluate thermal performance and system reliability. Findings indicate that elevated pressures contribute to better thermal conductivity, while higher flow rates enhance cooling capacity but shorten the coolant’s residence time. The stability of vessel wall temperatures across all test conditions highlights the effectiveness of the system’s insulation. These insights reinforce the TCR’s potential for application in next-generation, high-temperature nuclear systems.
"],"dc:identifier":["https://academicworks.cuny.edu/cc_etds_theses/1264"],"dc:subject":["Master","degree","TCR","Heat","Exchanger","Flow","Engineering"],"dc:title":["Experimental Characterization of Heat Transfer and Fluid Flow in TCR Fuel Elements under Varying Operational Conditions"],"thesis:degree_discipline":["Mechanical Engineering"],"thesis:degree_level":["Thesis"],"thesis:degree_name":["Master of Engineering (M.E.)"]},"updated_at":"2026-07-24T01:58:13Z"}