{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/113935"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/113935","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"Reactivity feedback analysis for EBR-II benchmark","abstract":"Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2022-04-06 without embargo terms","abstract_html":"Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2022-04-06 without embargo terms","abstract_has_math":false,"creators":["Chakinis, Michael"],"institution":"University of Illinois at Urbana-Champaign","degree_name":"M.S.","degree_level":"Thesis","degree_discipline":"Nuclear, Plasma, Radiolgc Engr","degree_department":null,"school":null,"contributors":["Kozlowski, Tomasz","Munk, Madicken"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2022,"date_issued":"2022-04-29T21:35:55Z","date_published":"2022-04-29T21:35:55Z","updated_at":"2026-07-22T22:24:53Z","subjects":["Engineering"],"languages":["en","eng"],"rights":["Copyright 2021 Michael Chakinis"],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/2142/113935","outbound_label":"Handle","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Kozlowski, Tomasz","Munk, Madicken"]},{"key":"dc:creator","label":"Author","values":["Chakinis, Michael"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2022-04-29T21:35:55Z","2021-12","2021-12-10"]},{"key":"dc:type","label":"Dc Type","values":["text","Thesis"]},{"key":"thesis:degree_discipline","label":"Discipline","values":["Nuclear, Plasma, Radiolgc Engr"]},{"key":"thesis:degree_level","label":"Degree Level","values":["Thesis"]},{"key":"thesis:degree_name","label":"Degree Name","values":["M.S."]},{"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"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["en","eng"]},{"key":"dc:rights","label":"Dc Rights","values":["Copyright 2021 Michael Chakinis"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["http://hdl.handle.net/2142/113935"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2022-04-06 without embargo terms","The student, Michael Chakinis, accepted the attached license on 2021-12-10 at 13:38.","The student, Michael Chakinis, submitted this Thesis for approval on 2021-12-10 at 13:43.","This Thesis was approved for publication on 2021-12-10 at 15:22.","DSpace SAF Submission Ingestion Package generated from Vireo submission #17449 on 2022-04-06 at 17:11:19","Made available in DSpace on 2022-04-29T21:35:55Z (GMT). No. of bitstreams: 3 CHAKINIS-THESIS-2021.pdf: 4401418 bytes, checksum: 78570e4c2691d49e1405151ed82d4300 (MD5) Michael Chakinis Masters Thesis Edited.zip: 10277005 bytes, checksum: e73edc6390f824604c6cac0198ce06af (MD5) LICENSE.txt: 4213 bytes, checksum: 1335f758f3aa04293efe733d2372866d (MD5) Previous issue date: 2021-12-10","The stability of a nuclear reactor is necessary to ensure its safety. Sodium-Cooled Fast Reactors have many desirable features that make them prime candidates for the future of small modular reactor design. These include higher operating temperatures for greater efficiency and lower pressures for safer power generation. Fast reactors rely on fast neutrons from fission which allow them to extend the use of uranium and thorium, operate at higher temperatures, and increase efficiency. This work uses the System Analysis Module, SAM, as the primary simulation tool developed by Argonne National Laboratory. Although SAM’s current capabilities are primarily focused on thermohydraulic analysis, this work studies extending the capability to point kinetics for analysis of reactivity feedbacks in sodium-cooled fast reactors. Multiphysics simulations like these are necessary for safety analysis of small modular reactors. Successful application of the point kinetics model can better help the understanding of reactivity feedbacks for safety analysis. The reactivity feedback model is based around the EBR-II reactor that was operated from INL. An analysis of core radial expansion, neutron Doppler shift, and coolant density during an unprotected loss-of-flow test, SHRT45R, are shown in this work. The specific test that is being analyzed is a Shutdown Heat Removal Test that occurred at the end of EBR-II’s lifespan. The uncertainty of the results are then calculated using the University of Illinois Urbana-Champaign developed tool, the Transient Analysis PackagE, TAPE. This thesis contributes to the future of both Argonne National Laboratory’s physics code capabilities and the utilization of UIUC’s uncertainty quantification tool. It is crucial that features necessary for determining the state of a nuclear reactor can be easily and accurately monitored. A negative total reactivity can result in the safe shutdown of a nuclear reactor during an unprotected-loss-of-flow scenario."]},{"key":"dc:format","label":"Dc Format","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["Reactivity feedback analysis for EBR-II benchmark"]}]}],"canonical_facts":{"dc:contributor":["Kozlowski, Tomasz","Munk, Madicken"],"dc:creator":["Chakinis, Michael"],"dc:date":["2022-04-29T21:35:55Z","2021-12","2021-12-10"],"dc:description":["Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2022-04-06 without embargo terms","The student, Michael Chakinis, accepted the attached license on 2021-12-10 at 13:38.","The student, Michael Chakinis, submitted this Thesis for approval on 2021-12-10 at 13:43.","This Thesis was approved for publication on 2021-12-10 at 15:22.","DSpace SAF Submission Ingestion Package generated from Vireo submission #17449 on 2022-04-06 at 17:11:19","Made available in DSpace on 2022-04-29T21:35:55Z (GMT). No. of bitstreams: 3 CHAKINIS-THESIS-2021.pdf: 4401418 bytes, checksum: 78570e4c2691d49e1405151ed82d4300 (MD5) Michael Chakinis Masters Thesis Edited.zip: 10277005 bytes, checksum: e73edc6390f824604c6cac0198ce06af (MD5) LICENSE.txt: 4213 bytes, checksum: 1335f758f3aa04293efe733d2372866d (MD5) Previous issue date: 2021-12-10","The stability of a nuclear reactor is necessary to ensure its safety. Sodium-Cooled Fast Reactors have many desirable features that make them prime candidates for the future of small modular reactor design. These include higher operating temperatures for greater efficiency and lower pressures for safer power generation. Fast reactors rely on fast neutrons from fission which allow them to extend the use of uranium and thorium, operate at higher temperatures, and increase efficiency. This work uses the System Analysis Module, SAM, as the primary simulation tool developed by Argonne National Laboratory. Although SAM’s current capabilities are primarily focused on thermohydraulic analysis, this work studies extending the capability to point kinetics for analysis of reactivity feedbacks in sodium-cooled fast reactors. Multiphysics simulations like these are necessary for safety analysis of small modular reactors. Successful application of the point kinetics model can better help the understanding of reactivity feedbacks for safety analysis. The reactivity feedback model is based around the EBR-II reactor that was operated from INL. An analysis of core radial expansion, neutron Doppler shift, and coolant density during an unprotected loss-of-flow test, SHRT45R, are shown in this work. The specific test that is being analyzed is a Shutdown Heat Removal Test that occurred at the end of EBR-II’s lifespan. The uncertainty of the results are then calculated using the University of Illinois Urbana-Champaign developed tool, the Transient Analysis PackagE, TAPE. This thesis contributes to the future of both Argonne National Laboratory’s physics code capabilities and the utilization of UIUC’s uncertainty quantification tool. It is crucial that features necessary for determining the state of a nuclear reactor can be easily and accurately monitored. A negative total reactivity can result in the safe shutdown of a nuclear reactor during an unprotected-loss-of-flow scenario."],"dc:format":["application/pdf"],"dc:identifier":["http://hdl.handle.net/2142/113935"],"dc:language":["en","eng"],"dc:rights":["Copyright 2021 Michael Chakinis"],"dc:subject":["Engineering"],"dc:title":["Reactivity feedback analysis for EBR-II benchmark"],"dc:type":["text","Thesis"],"thesis:degree_discipline":["Nuclear, Plasma, Radiolgc Engr"],"thesis:degree_level":["Thesis"],"thesis:degree_name":["M.S."],"thesis:institution_name":["University of Illinois at Urbana-Champaign"]},"updated_at":"2026-07-22T22:24:53Z"}