{"id":{"repo_id":"uiuc","oai_identifier":"oai:www.ideals.illinois.edu:2142/102413"},"canonical_url":"https://search.dev.ndltd.org/etd/uiuc/oai:www.ideals.illinois.edu:2142/102413","repository":{"repo_id":"uiuc","name":"University of Illinois - Urbana-Champaign","base_url":"https://www.ideals.illinois.edu/oai-pmh"},"display":{"title":"Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS","abstract":"This thesis is a comprehensive study on the effect load-follow operation has on fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be negligible after two cycles of depletion. Both low power physics tests and critical boron comparisons show excellent agreement between the VERA-CS predictions and the plant-measured data after cycle 19. In addition to cycle depletion, five load-follow power maneuvers in the first 24 days of cycle 21 were simulated using hourly depletion steps. Predictions showed an overestimation of the axial offset behavior during the load-follow operation but the overall reactivity of the core was in good agreement. The linear heat rate and coolant temperature calculated by VERA-CS were used as boundary conditions for BISON fuel performance calculations. Using the maximum hoop stress as the indicator of fuel failure risk, the different load-follow power maneuvers were compared to the initial start-up ramp. The maximum clad hoop stress occurred during the start-up ramp and was estimated to be 94 MPa, the subsequent maneuvers showed similar magnitudes regardless of the change in power. No correlation was observed between the characteristics of the load-follow power maneuver and the resulting maximum clad hoop stress. Neither the magnitude of the decrease in power, hold period, nor intermediate power steps showed a variation in the maximum clad hoop stress observed after a return to full power this early in the cycle. To reduce the number of fuel performance calculations required to determine the safety of a power maneuver, a screening process was developed based on a weighted change in conditioned power. By selecting the top 1000 fuel rods showing a positive weighted change in linear heat rate, the limiting fuel pin for the maneuver is included, with most of the selected pins showing elevated hoop stresses.","abstract_html":"This thesis is a comprehensive study on the effect load-follow operation has on fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be negligible after two cycles of depletion. Both low power physics tests and critical boron comparisons show excellent agreement between the VERA-CS predictions and the plant-measured data after cycle 19. In addition to cycle depletion, five load-follow power maneuvers in the first 24 days of cycle 21 were simulated using hourly depletion steps. Predictions showed an overestimation of the axial offset behavior during the load-follow operation but the overall reactivity of the core was in good agreement. The linear heat rate and coolant temperature calculated by VERA-CS were used as boundary conditions for BISON fuel performance calculations. Using the maximum hoop stress as the indicator of fuel failure risk, the different load-follow power maneuvers were compared to the initial start-up ramp. The maximum clad hoop stress occurred during the start-up ramp and was estimated to be 94 MPa, the subsequent maneuvers showed similar magnitudes regardless of the change in power. No correlation was observed between the characteristics of the load-follow power maneuver and the resulting maximum clad hoop stress. Neither the magnitude of the decrease in power, hold period, nor intermediate power steps showed a variation in the maximum clad hoop stress observed after a return to full power this early in the cycle. To reduce the number of fuel performance calculations required to determine the safety of a power maneuver, a screening process was developed based on a weighted change in conditioned power. By selecting the top 1000 fuel rods showing a positive weighted change in linear heat rate, the limiting fuel pin for the maneuver is included, with most of the selected pins showing elevated hoop stresses.","abstract_has_math":false,"creators":["O'Grady, Daniel John"],"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","Huff, Kathryn"],"advisors":[],"committee_chairs":[],"committee_members":[],"year":2019,"date_issued":"2019-02-06T19:32:45Z","date_published":"2019-02-06T19:32:45Z","updated_at":"2026-07-22T22:24:40Z","subjects":["Pellet-Clad Material Interaction","Load-follow operation","VERA-CS","BISON"],"languages":["en"],"rights":["Copyright 2018 Daniel John O'Grady"],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"http://hdl.handle.net/2142/102413","outbound_label":"Handle","outbound_source":"dc:identifier"},"metadata_groups":[{"id":"people","label":"People","entries":[{"key":"dc:contributor","label":"Contributor","values":["Kozlowski, Tomasz","Huff, Kathryn"]},{"key":"dc:creator","label":"Author","values":["O'Grady, Daniel John"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date","label":"Dc Date","values":["2019-02-06T19:32:45Z","2018-10-25","2018-12"]},{"key":"dc:type","label":"Dc Type","values":["text"]},{"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":["Pellet-Clad Material Interaction","Load-follow operation","VERA-CS","BISON"]}]},{"id":"language_rights","label":"Language and Rights","entries":[{"key":"dc:language","label":"Dc Language","values":["en"]},{"key":"dc:rights","label":"Dc Rights","values":["Copyright 2018 Daniel John O'Grady"]}]},{"id":"identifiers","label":"Identifiers","entries":[{"key":"dc:identifier","label":"Identifier","values":["http://hdl.handle.net/2142/102413"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description","label":"Description","values":["This thesis is a comprehensive study on the effect load-follow operation has on fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be negligible after two cycles of depletion. Both low power physics tests and critical boron comparisons show excellent agreement between the VERA-CS predictions and the plant-measured data after cycle 19. In addition to cycle depletion, five load-follow power maneuvers in the first 24 days of cycle 21 were simulated using hourly depletion steps. Predictions showed an overestimation of the axial offset behavior during the load-follow operation but the overall reactivity of the core was in good agreement. The linear heat rate and coolant temperature calculated by VERA-CS were used as boundary conditions for BISON fuel performance calculations. Using the maximum hoop stress as the indicator of fuel failure risk, the different load-follow power maneuvers were compared to the initial start-up ramp. The maximum clad hoop stress occurred during the start-up ramp and was estimated to be 94 MPa, the subsequent maneuvers showed similar magnitudes regardless of the change in power. No correlation was observed between the characteristics of the load-follow power maneuver and the resulting maximum clad hoop stress. Neither the magnitude of the decrease in power, hold period, nor intermediate power steps showed a variation in the maximum clad hoop stress observed after a return to full power this early in the cycle. To reduce the number of fuel performance calculations required to determine the safety of a power maneuver, a screening process was developed based on a weighted change in conditioned power. By selecting the top 1000 fuel rods showing a positive weighted change in linear heat rate, the limiting fuel pin for the maneuver is included, with most of the selected pins showing elevated hoop stresses.","Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2019-02-05 without embargo terms","The student, Daniel O'Grady, accepted the attached license on 2018-10-23 at 16:41.","The student, Daniel O'Grady, submitted this Thesis for approval on 2018-10-23 at 16:56.","This Thesis was approved for publication on 2018-10-25 at 13:56.","DSpace SAF Submission Ingestion Package generated from Vireo submission #13038 on 2019-02-05 at 11:08:25","Made available in DSpace on 2019-02-06T19:32:45Z (GMT). No. of bitstreams: 2 OGRADY-THESIS-2018.pdf: 9124448 bytes, checksum: 0b7588b8089509cf860029bd5d55e721 (MD5) LICENSE.txt: 4211 bytes, checksum: 335148eba0844e20a8059edc4d5fbba8 (MD5) Previous issue date: 2018-10-25"]},{"key":"dc:format","label":"Dc Format","values":["application/pdf"]},{"key":"dc:title","label":"Title","values":["Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS"]}]}],"canonical_facts":{"dc:contributor":["Kozlowski, Tomasz","Huff, Kathryn"],"dc:creator":["O'Grady, Daniel John"],"dc:date":["2019-02-06T19:32:45Z","2018-10-25","2018-12"],"dc:description":["This thesis is a comprehensive study on the effect load-follow operation has on fuel failure risk in a PWR. PWR1, a commercial reactor that performed load-follow power maneuvers in cycle 21, was modeled using VERA-CS. The effects of a jump-in approach, starting depletion in cycle 17 as compared to cycle 1, were shown to be negligible after two cycles of depletion. Both low power physics tests and critical boron comparisons show excellent agreement between the VERA-CS predictions and the plant-measured data after cycle 19. In addition to cycle depletion, five load-follow power maneuvers in the first 24 days of cycle 21 were simulated using hourly depletion steps. Predictions showed an overestimation of the axial offset behavior during the load-follow operation but the overall reactivity of the core was in good agreement. The linear heat rate and coolant temperature calculated by VERA-CS were used as boundary conditions for BISON fuel performance calculations. Using the maximum hoop stress as the indicator of fuel failure risk, the different load-follow power maneuvers were compared to the initial start-up ramp. The maximum clad hoop stress occurred during the start-up ramp and was estimated to be 94 MPa, the subsequent maneuvers showed similar magnitudes regardless of the change in power. No correlation was observed between the characteristics of the load-follow power maneuver and the resulting maximum clad hoop stress. Neither the magnitude of the decrease in power, hold period, nor intermediate power steps showed a variation in the maximum clad hoop stress observed after a return to full power this early in the cycle. To reduce the number of fuel performance calculations required to determine the safety of a power maneuver, a screening process was developed based on a weighted change in conditioned power. By selecting the top 1000 fuel rods showing a positive weighted change in linear heat rate, the limiting fuel pin for the maneuver is included, with most of the selected pins showing elevated hoop stresses.","Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2019-02-05 without embargo terms","The student, Daniel O'Grady, accepted the attached license on 2018-10-23 at 16:41.","The student, Daniel O'Grady, submitted this Thesis for approval on 2018-10-23 at 16:56.","This Thesis was approved for publication on 2018-10-25 at 13:56.","DSpace SAF Submission Ingestion Package generated from Vireo submission #13038 on 2019-02-05 at 11:08:25","Made available in DSpace on 2019-02-06T19:32:45Z (GMT). No. of bitstreams: 2 OGRADY-THESIS-2018.pdf: 9124448 bytes, checksum: 0b7588b8089509cf860029bd5d55e721 (MD5) LICENSE.txt: 4211 bytes, checksum: 335148eba0844e20a8059edc4d5fbba8 (MD5) Previous issue date: 2018-10-25"],"dc:format":["application/pdf"],"dc:identifier":["http://hdl.handle.net/2142/102413"],"dc:language":["en"],"dc:rights":["Copyright 2018 Daniel John O'Grady"],"dc:subject":["Pellet-Clad Material Interaction","Load-follow operation","VERA-CS","BISON"],"dc:title":["Investigation of pellet-clad interaction during load-follow operation in a pressurized water reactor using VERA-CS"],"dc:type":["text"],"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":"2026-07-22T22:24:40Z"}