“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing the safety analysis and GCR technologies are required for the optimum design and safety of GCR system. Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Science and Technology (S&T) has developed a natural convection heat transfer test facility with one riser and one downcomer between two plena to investigate loss of flow accident scenario (LOFA) for a prismatic very high temperature reactor (VHTR). Using advanced heat transfer coefficient probe and T-thermocouples. The facility represents a scaled down prismatic modular reactor with a reference to High-Temperature Test Facility at Oregon State University (OSU-HTTF). The natural circulation heat transfer in terms of temperature fields and heat transfer coefficients across the core of current facility (i.e., channels) has been investigated at different conditions to understand the passive safety features of prismatic modular reactors (PMR). This dissertation advance knowledge and understanding of the intra core natural circulation phenomenon in the PMRs. Moreover, fill the gaps in the open literature and understanding of the natural circulation heat transfer and gaseous dynamics in the prismatic VHTR and provide experimental benchmark data, which is much needed and is missing in the literature for verification and validation”--Abstract, page iii.
","abstract_html":"<p>“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing the safety analysis and GCR technologies are required for the optimum design and safety of GCR system. Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Science and Technology (S&T) has developed a natural convection heat transfer test facility with one riser and one downcomer between two plena to investigate loss of flow accident scenario (LOFA) for a prismatic very high temperature reactor (VHTR). Using advanced heat transfer coefficient probe and T-thermocouples. The facility represents a scaled down prismatic modular reactor with a reference to High-Temperature Test Facility at Oregon State University (OSU-HTTF). The natural circulation heat transfer in terms of temperature fields and heat transfer coefficients across the core of current facility (i.e., channels) has been investigated at different conditions to understand the passive safety features of prismatic modular reactors (PMR). This dissertation advance knowledge and understanding of the intra core natural circulation phenomenon in the PMRs. Moreover, fill the gaps in the open literature and understanding of the natural circulation heat transfer and gaseous dynamics in the prismatic VHTR and provide experimental benchmark data, which is much needed and is missing in the literature for verification and validation”--Abstract, page iii.</p>","abstract_has_math":false,"creators":["Alshehri, Salman Mohammed"],"institution":"Missouri University of Science and Technology","degree_name":"Ph. D. in Nuclear Engineering","degree_level":null,"degree_discipline":null,"degree_department":null,"school":null,"contributors":[],"advisors":[],"committee_chairs":[],"committee_members":[],"year":null,"date_issued":"","date_published":null,"updated_at":"2026-07-24T03:18:09Z","subjects":["Advanced Heat Transfer Probe","Heat Transfer Coefficient","Natural Convection","Nonuniform Heat","Nusselt Number","Prismatic Modular Reactor","Chemical Engineering","Mechanical Engineering","Nuclear Engineering"],"languages":[],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://scholarsmine.mst.edu/doctoral_dissertations/3123","outbound_label":"Repository record","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:creator","label":"Author","values":["Alshehri, Salman Mohammed"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:type","label":"Dc Type","values":["Dissertation - Open Access"]},{"key":"thesis:degree_name","label":"Degree Name","values":["Ph. D. in Nuclear Engineering"]},{"key":"thesis:institution_name","label":"Thesis Institution Name","values":["Missouri University of Science and Technology"]}]},{"id":"subjects_keywords","label":"Subjects and Keywords","entries":[{"key":"dc:subject","label":"Dc Subject","values":["Advanced Heat Transfer Probe","Heat Transfer Coefficient","Natural Convection","Nonuniform Heat","Nusselt Number","Prismatic Modular Reactor","Chemical Engineering","Mechanical Engineering","Nuclear Engineering"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["https://scholarsmine.mst.edu/doctoral_dissertations/3123"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing the safety analysis and GCR technologies are required for the optimum design and safety of GCR system. Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Science and Technology (S&T) has developed a natural convection heat transfer test facility with one riser and one downcomer between two plena to investigate loss of flow accident scenario (LOFA) for a prismatic very high temperature reactor (VHTR). Using advanced heat transfer coefficient probe and T-thermocouples. The facility represents a scaled down prismatic modular reactor with a reference to High-Temperature Test Facility at Oregon State University (OSU-HTTF). The natural circulation heat transfer in terms of temperature fields and heat transfer coefficients across the core of current facility (i.e., channels) has been investigated at different conditions to understand the passive safety features of prismatic modular reactors (PMR). This dissertation advance knowledge and understanding of the intra core natural circulation phenomenon in the PMRs. Moreover, fill the gaps in the open literature and understanding of the natural circulation heat transfer and gaseous dynamics in the prismatic VHTR and provide experimental benchmark data, which is much needed and is missing in the literature for verification and validation”--Abstract, page iii.
"]},{"key":"dc:title","label":"Title","values":["Plenum-to-plenum heat transfer characteristics under natural circulation in a scaled-down prismatic modular reactor"]}]}],"canonical_facts":{"dc:creator":["Alshehri, Salman Mohammed"],"dc:description.abstract":["“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a promising solution, particularly the possibility of producing hydrogen. Studying and developing the safety analysis and GCR technologies are required for the optimum design and safety of GCR system. Multiphase Reactors Engineering and Applications Laboratory (mReal) at Missouri University of Science and Technology (S&T) has developed a natural convection heat transfer test facility with one riser and one downcomer between two plena to investigate loss of flow accident scenario (LOFA) for a prismatic very high temperature reactor (VHTR). Using advanced heat transfer coefficient probe and T-thermocouples. The facility represents a scaled down prismatic modular reactor with a reference to High-Temperature Test Facility at Oregon State University (OSU-HTTF). The natural circulation heat transfer in terms of temperature fields and heat transfer coefficients across the core of current facility (i.e., channels) has been investigated at different conditions to understand the passive safety features of prismatic modular reactors (PMR). This dissertation advance knowledge and understanding of the intra core natural circulation phenomenon in the PMRs. Moreover, fill the gaps in the open literature and understanding of the natural circulation heat transfer and gaseous dynamics in the prismatic VHTR and provide experimental benchmark data, which is much needed and is missing in the literature for verification and validation”--Abstract, page iii.
"],"dc:identifier":["https://scholarsmine.mst.edu/doctoral_dissertations/3123"],"dc:subject":["Advanced Heat Transfer Probe","Heat Transfer Coefficient","Natural Convection","Nonuniform Heat","Nusselt Number","Prismatic Modular Reactor","Chemical Engineering","Mechanical Engineering","Nuclear Engineering"],"dc:title":["Plenum-to-plenum heat transfer characteristics under natural circulation in a scaled-down prismatic modular reactor"],"dc:type":["Dissertation - Open Access"],"thesis:degree_name":["Ph. D. in Nuclear Engineering"],"thesis:institution_name":["Missouri University of Science and Technology"]},"updated_at":"2026-07-24T03:18:09Z"}