Baker, Fiona Christine2024-10-032024-10-032024-08https://unbscholar.lib.unb.ca/handle/1882/38138During nuclear reactor operation, dissolved and particulate corrosion products release from component walls followed by transport to the reactor core, where they deposit on fuel channels, undergoing irradiation for a certain residence time under the neutron flux. These corrosion products are released from the core and deposit throughout the primary heat transport system (PHTS). The Corrosion and Radioactivity Transport Analysis (CARTA) code is a predictive tool that uses a mechanistic approach to model surface and bulk activity within the PHTS of a Canada Deuterium Uranium (CANDU)-6 reactor. Two sources of radionuclide transport are modelled: a dissolved cobalt input term due to mechanical wear of the refuelling machine, and an out-of-core input due to changes from precipitation to dissolution in the steam generators, where previously deposited radionuclides are released from legacy deposits. These additions strengthen the code's adaptability to station events when simulating the kinetics of material release and activation processes.xiv, 100electronicenhttp://purl.org/coar/access_right/c_abf2master thesisPalazhchenko, OlgaChemical Engineering