{"id":{"repo_id":"uoit","oai_identifier":"oai:ontariotechu.scholaris.ca:10155/116"},"canonical_url":"https://search.dev.ndltd.org/etd/uoit/oai:ontariotechu.scholaris.ca:10155/116","repository":{"repo_id":"uoit","name":"Ontario Institute of Technology","base_url":"https://ontariotechu.scholaris.ca/server/oai/request"},"display":{"title":"Three dimensional heterogeneous finite element method for static multi-group neutron diffusion","abstract":"Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A three-dimensional Heterogeneous Finite Element Method (HFEM) is developed to address the limitations of current methods by offering fine-group energy representation and fuel-pin-level spatial detail at modest computational cost. The calculational cost of the method is roughly equal to the calculational cost of the Finite Differences Method (FDM) using one mesh box per fuel assembly and a comparable number of energy groups. Pin-level fluxes are directly obtained from the method’s results without the need for reconstruction schemes.","abstract_html":"Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A three-dimensional Heterogeneous Finite Element Method (HFEM) is developed to address the limitations of current methods by offering fine-group energy representation and fuel-pin-level spatial detail at modest computational cost. The calculational cost of the method is roughly equal to the calculational cost of the Finite Differences Method (FDM) using one mesh box per fuel assembly and a comparable number of energy groups. Pin-level fluxes are directly obtained from the method’s results without the need for reconstruction schemes.","abstract_has_math":false,"creators":["Aydogdu, Elif Can"],"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 M."],"committee_chairs":[],"committee_members":[],"year":2010,"date_issued":"2010-08-01","date_published":"2010-08-01","updated_at":"2026-07-24T05:35:41Z","subjects":["Heterogeneous finite element method","Static neutron diffusion equation","Finite difference equations","Weighted residuals method"],"languages":["en"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10155/116","outbound_label":"Handle","outbound_source":"dc:identifier.uri"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor.advisor","label":"Advisor","values":["Nichita, Eleodor M."]},{"key":"dc:creator","label":"Author","values":["Aydogdu, Elif Can"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2010-10-14T18:26:20Z","2022-03-25T18:48:52Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2010-10-14T18:26:20Z","2022-03-25T18:48:52Z"]},{"key":"dc:date.issued","label":"Date","values":["2010-08-01"]},{"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":["Heterogeneous finite element method","Static neutron diffusion equation","Finite difference equations","Weighted residuals method"]}]},{"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/10155/116"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A three-dimensional Heterogeneous Finite Element Method (HFEM) is developed to address the limitations of current methods by offering fine-group energy representation and fuel-pin-level spatial detail at modest computational cost. The calculational cost of the method is roughly equal to the calculational cost of the Finite Differences Method (FDM) using one mesh box per fuel assembly and a comparable number of energy groups. Pin-level fluxes are directly obtained from the method’s results without the need for reconstruction schemes."]},{"key":"dc:title","label":"Title","values":["Three dimensional heterogeneous finite element method for static multi-group neutron diffusion"]}]}],"canonical_facts":{"dc:contributor.advisor":["Nichita, Eleodor M."],"dc:creator":["Aydogdu, Elif Can"],"dc:date.accessioned":["2010-10-14T18:26:20Z","2022-03-25T18:48:52Z"],"dc:date.available":["2010-10-14T18:26:20Z","2022-03-25T18:48:52Z"],"dc:date.issued":["2010-08-01"],"dc:description.abstract":["Because current full-core neutronic-calculations use two-group neutron diffusion and rely on homogenizing fuel assemblies, reconstructing pin powers from such a calculation is an elaborate and not very accurate process; one which becomes more difficult with increased core heterogeneity. A three-dimensional Heterogeneous Finite Element Method (HFEM) is developed to address the limitations of current methods by offering fine-group energy representation and fuel-pin-level spatial detail at modest computational cost. The calculational cost of the method is roughly equal to the calculational cost of the Finite Differences Method (FDM) using one mesh box per fuel assembly and a comparable number of energy groups. Pin-level fluxes are directly obtained from the method’s results without the need for reconstruction schemes."],"dc:identifier.uri":["https://hdl.handle.net/10155/116"],"dc:language.iso":["en"],"dc:subject":["Heterogeneous finite element method","Static neutron diffusion equation","Finite difference equations","Weighted residuals method"],"dc:title":["Three dimensional heterogeneous finite element method for static multi-group neutron diffusion"],"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":"2026-07-24T05:35:41Z"}