{"id":{"repo_id":"uoit","oai_identifier":"oai:ontariotechu.scholaris.ca:10155/415"},"canonical_url":"https://search.dev.ndltd.org/etd/uoit/oai:ontariotechu.scholaris.ca:10155/415","repository":{"repo_id":"uoit","name":"Ontario Institute of Technology","base_url":"https://ontariotechu.scholaris.ca/server/oai/request"},"display":{"title":"Simulation of dynamic response of Self-Powered-Inconel-Neutron-Detector lead cables using a semi-empirical model","abstract":"The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical dynamic model of theInconel lead-cables in Ontario Power Generation’s Darlington Nuclear GenerationStation (NGS) able to simulate the lead cables’ response to arbitrary neutron-fluxtransients. A secondary goal was to compare lead-cable dynamic characteristicsevaluated in the Darlington reactor to lead-cable characteristics previously evaluated inAECL’s NRU reactor.A Simulink model of the lead cable was developed. The model’s parameterswere obtained by fitting simulation results to measured lead-cable signals acquiredduring reactor shutdown. The functionality of the Simulink model was demonstrated forarbitrary neutron flux transients and simulation results were found to agree within 1.2%with measurements for reactor trip transients. At the same time, differences between thedynamic characteristics (e.g. prompt fraction) of lead cables in a power reactor(Darlington) and research reactor (NRU) were identified. A tentative explanation ofthose differences was formulated. A comprehensive elucidation of the reasons for the observed differences will have to be addressed by future studies.","abstract_html":"The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical dynamic model of theInconel lead-cables in Ontario Power Generation’s Darlington Nuclear GenerationStation (NGS) able to simulate the lead cables’ response to arbitrary neutron-fluxtransients. A secondary goal was to compare lead-cable dynamic characteristicsevaluated in the Darlington reactor to lead-cable characteristics previously evaluated inAECL’s NRU reactor.A Simulink model of the lead cable was developed. The model’s parameterswere obtained by fitting simulation results to measured lead-cable signals acquiredduring reactor shutdown. The functionality of the Simulink model was demonstrated forarbitrary neutron flux transients and simulation results were found to agree within 1.2%with measurements for reactor trip transients. At the same time, differences between thedynamic characteristics (e.g. prompt fraction) of lead cables in a power reactor(Darlington) and research reactor (NRU) were identified. A tentative explanation ofthose differences was formulated. A comprehensive elucidation of the reasons for the observed differences will have to be addressed by future studies.","abstract_has_math":false,"creators":["Yu, Jin"],"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":2013,"date_issued":"2013-11-01","date_published":"2013-11-01","updated_at":"2026-07-24T05:35:36Z","subjects":["Lead cable","Detector","Inconel","Simulation"],"languages":["en"],"rights":[],"rights_urls":[],"identifier_entries":[]},"links":{"outbound_url":"https://hdl.handle.net/10155/415","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":["Yu, Jin"]}]},{"id":"academic_context","label":"Academic Context","entries":[{"key":"dc:date.accessioned","label":"Dc Date Accessioned","values":["2014-04-14T18:53:00Z","2022-03-25T18:49:01Z"]},{"key":"dc:date.available","label":"Dc Date Available","values":["2014-04-14T18:53:00Z","2022-03-25T18:49:01Z"]},{"key":"dc:date.issued","label":"Date","values":["2013-11-01"]},{"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":["Lead cable","Detector","Inconel","Simulation"]}]},{"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/10155/415"]}]},{"id":"additional","label":"Additional Metadata","entries":[{"key":"dc:description.abstract","label":"Abstract","values":["The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical dynamic model of theInconel lead-cables in Ontario Power Generation’s Darlington Nuclear GenerationStation (NGS) able to simulate the lead cables’ response to arbitrary neutron-fluxtransients. A secondary goal was to compare lead-cable dynamic characteristicsevaluated in the Darlington reactor to lead-cable characteristics previously evaluated inAECL’s NRU reactor.A Simulink model of the lead cable was developed. The model’s parameterswere obtained by fitting simulation results to measured lead-cable signals acquiredduring reactor shutdown. The functionality of the Simulink model was demonstrated forarbitrary neutron flux transients and simulation results were found to agree within 1.2%with measurements for reactor trip transients. At the same time, differences between thedynamic characteristics (e.g. prompt fraction) of lead cables in a power reactor(Darlington) and research reactor (NRU) were identified. A tentative explanation ofthose differences was formulated. A comprehensive elucidation of the reasons for the observed differences will have to be addressed by future studies."]},{"key":"dc:title","label":"Title","values":["Simulation of dynamic response of Self-Powered-Inconel-Neutron-Detector lead cables using a semi-empirical model"]}]}],"canonical_facts":{"dc:contributor.advisor":["Nichita, Eleodor"],"dc:creator":["Yu, Jin"],"dc:date.accessioned":["2014-04-14T18:53:00Z","2022-03-25T18:49:01Z"],"dc:date.available":["2014-04-14T18:53:00Z","2022-03-25T18:49:01Z"],"dc:date.issued":["2013-11-01"],"dc:description.abstract":["The work presented here was devoted to the modelling and simulation of the dynamic response of lead cables of Inconel self-powered neutron detectors in a CANDUpower reactor. The main goal was to develop a semi-empirical dynamic model of theInconel lead-cables in Ontario Power Generation’s Darlington Nuclear GenerationStation (NGS) able to simulate the lead cables’ response to arbitrary neutron-fluxtransients. A secondary goal was to compare lead-cable dynamic characteristicsevaluated in the Darlington reactor to lead-cable characteristics previously evaluated inAECL’s NRU reactor.A Simulink model of the lead cable was developed. The model’s parameterswere obtained by fitting simulation results to measured lead-cable signals acquiredduring reactor shutdown. The functionality of the Simulink model was demonstrated forarbitrary neutron flux transients and simulation results were found to agree within 1.2%with measurements for reactor trip transients. At the same time, differences between thedynamic characteristics (e.g. prompt fraction) of lead cables in a power reactor(Darlington) and research reactor (NRU) were identified. A tentative explanation ofthose differences was formulated. A comprehensive elucidation of the reasons for the observed differences will have to be addressed by future studies."],"dc:identifier.uri":["https://hdl.handle.net/10155/415"],"dc:language.iso":["en"],"dc:subject":["Lead cable","Detector","Inconel","Simulation"],"dc:title":["Simulation of dynamic response of Self-Powered-Inconel-Neutron-Detector lead cables using a semi-empirical model"],"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":"2026-07-24T05:35:36Z"}