{"id":{"repo_id":"uoit","oai_identifier":"oai:ontariotechu.scholaris.ca:10155/455"},"canonical_url":"https://search.dev.ndltd.org/etd/uoit/oai:ontariotechu.scholaris.ca:10155/455","repository":{"repo_id":"uoit","name":"Ontario Institute of Technology","base_url":"https://ontariotechu.scholaris.ca/server/oai/request"},"display":{"title":"Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors.","abstract":"In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU type power reactors are explored. Since Mo-99 is generated by the fission of U-235 with a fission yield of 6.1%, the proposed designs use enriched uranium in the Mo-99 producing fuel pins. The challenge lies in designing a fuel that is able to produce significant quantities of Mo-99 while having similar neutronics and thermalhydraulic characteristics to the standard CANDU fuel. The proposed designs, when irradiated in the peak power channel of a CANDU core, are shown to produce significant quantities of Mo-99 while maintaining the necessary reactivity and power rating limits. The total Mo-99 production activities are found to be approximately 2335, 2297, 2336, 4131 and 4268 six-day Curies per bundle for Designs 1 to 5, respectively. The yield corresponds to approximately 19% (for Designs 1, 2 and 3) and 34% (for Designs 4 and 5) of the world weekly demand for Mo-99. A production cycle of 6 bundles per week (for Designs 1, 2 and 3), or 3 bundles per week (for Designs 4 and 5) can meet the global demand of Mo-99 medical isotopes.","abstract_html":"In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU type power reactors are explored. Since Mo-99 is generated by the fission of U-235 with a fission yield of 6.1%, the proposed designs use enriched uranium in the Mo-99 producing fuel pins. The challenge lies in designing a fuel that is able to produce significant quantities of Mo-99 while having similar neutronics and thermalhydraulic characteristics to the standard CANDU fuel. The proposed designs, when irradiated in the peak power channel of a CANDU core, are shown to produce significant quantities of Mo-99 while maintaining the necessary reactivity and power rating limits. The total Mo-99 production activities are found to be approximately 2335, 2297, 2336, 4131 and 4268 six-day Curies per bundle for Designs 1 to 5, respectively. The yield corresponds to approximately 19% (for Designs 1, 2 and 3) and 34% (for Designs 4 and 5) of the world weekly demand for Mo-99. A production cycle of 6 bundles per week (for Designs 1, 2 and 3), or 3 bundles per week (for Designs 4 and 5) can meet the global demand of Mo-99 medical isotopes.","abstract_has_math":false,"creators":["Haroon, Jawad"],"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":["Nichita, Eleodor"],"committee_chairs":[],"committee_members":[],"year":2014,"date_issued":"2014-08-01","date_published":"2014-08-01","updated_at":"2026-07-24T05:35:28Z","subjects":["Medical isotopes","CANDU","Molybdenum-99","Six-day curies","Linear heat rating"],"languages":["en"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10155/455","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Nichita, Eleodor"]},{"key":"dc:creator","label":"Author","values":["Haroon, Jawad"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2014-09-23T18:36:02Z","2022-03-25T18:48:52Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2014-09-23T18:36:02Z","2022-03-25T18:48:52Z"]},{"key":"dc:date.issued","label":"Date","values":["2014-08-01"]},{"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":["Medical isotopes","CANDU","Molybdenum-99","Six-day curies","Linear heat rating"]}]},{"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/10155/455"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU type power reactors are explored. Since Mo-99 is generated by the fission of U-235 with a fission yield of 6.1%, the proposed designs use enriched uranium in the Mo-99 producing fuel pins. The challenge lies in designing a fuel that is able to produce significant quantities of Mo-99 while having similar neutronics and thermalhydraulic characteristics to the standard CANDU fuel. The proposed designs, when irradiated in the peak power channel of a CANDU core, are shown to produce significant quantities of Mo-99 while maintaining the necessary reactivity and power rating limits. The total Mo-99 production activities are found to be approximately 2335, 2297, 2336, 4131 and 4268 six-day Curies per bundle for Designs 1 to 5, respectively. The yield corresponds to approximately 19% (for Designs 1, 2 and 3) and 34% (for Designs 4 and 5) of the world weekly demand for Mo-99. A production cycle of 6 bundles per week (for Designs 1, 2 and 3), or 3 bundles per week (for Designs 4 and 5) can meet the global demand of Mo-99 medical isotopes."]},{"key":"dc:title","label":"Title","values":["Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors."]}]}],"canonical_facts":{"dc:contributor.advisor":["Nichita, Eleodor"],"dc:creator":["Haroon, Jawad"],"dc:date.accessioned":["2014-09-23T18:36:02Z","2022-03-25T18:48:52Z"],"dc:date.available":["2014-09-23T18:36:02Z","2022-03-25T18:48:52Z"],"dc:date.issued":["2014-08-01"],"dc:description.abstract":["In this study, the potential use of CANDU power reactors for the production of Mo-99 is assessed. Five different modifications of a 37-element fuel bundle that could be used for the production of Mo-99 in existing CANDU type power reactors are explored. Since Mo-99 is generated by the fission of U-235 with a fission yield of 6.1%, the proposed designs use enriched uranium in the Mo-99 producing fuel pins. The challenge lies in designing a fuel that is able to produce significant quantities of Mo-99 while having similar neutronics and thermalhydraulic characteristics to the standard CANDU fuel. The proposed designs, when irradiated in the peak power channel of a CANDU core, are shown to produce significant quantities of Mo-99 while maintaining the necessary reactivity and power rating limits. The total Mo-99 production activities are found to be approximately 2335, 2297, 2336, 4131 and 4268 six-day Curies per bundle for Designs 1 to 5, respectively. The yield corresponds to approximately 19% (for Designs 1, 2 and 3) and 34% (for Designs 4 and 5) of the world weekly demand for Mo-99. A production cycle of 6 bundles per week (for Designs 1, 2 and 3), or 3 bundles per week (for Designs 4 and 5) can meet the global demand of Mo-99 medical isotopes."],"dc:identifier.uri":["https://hdl.handle.net/10155/455"],"dc:language.iso":["en"],"dc:subject":["Medical isotopes","CANDU","Molybdenum-99","Six-day curies","Linear heat rating"],"dc:title":["Development of a 37-element fuel bundle for the production of molybdenum-99 in CANDU power reactors."],"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":"2026-07-24T05:35:28Z"}