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Please use this identifier to cite or link to this item: http://hdl.handle.net/11375/28246
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dc.contributor.advisorNovog, David-
dc.contributor.authorYounan, Simon-
dc.date.accessioned2023-01-25T16:16:12Z-
dc.date.available2023-01-25T16:16:12Z-
dc.date.issued2022-
dc.identifier.urihttp://hdl.handle.net/11375/28246-
dc.descriptionMcMaster University DOCTOR OF PHILOSOPHY (2022) Hamilton, Ontario (Engineering Physics) TITLE: Development and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysis AUTHOR: Simon Younan, M.A.Sc. (McMaster University), B.Eng. (McMaster University) SUPERVISOR: Dr. David Novog NUMBER OF PAGES: xiv, 163en_US
dc.description.abstractIn the field of nuclear safety analysis, as computers have become more powerful, there has been a trend away from low-fidelity models using conservative assumptions, to high-fidelity best-estimate models combined with uncertainty analysis. A number of these tools have been developed in the United States, due to the popularity of light water reactors. These include the SCALE analysis suite developed by ORNL, as well as the PARCS and TRACE tools backed by the USNRC. This work explores adapting the capabilities of these tools to the analysis of CANDU reactors. The Polaris sequence, introduced in SCALE 6.2, was extended in this work to support CANDU geometries and compared to existing SCALE sequences such as TRITON. Emphasis was placed on the Embedded Self-Shielding Method (ESSM), introduced with Polaris. Both Polaris and ESSM were evaluated and found to perform adequately for CANDU geometries. The accuracy of ESSM was found to improve when the precomputed selfshielding factors were updated using a CANDU representation. The PARCS diffusion code and the TRACE system thermalhydraulics code were coupled, using the built-in coupling capability between the two codes. In addition, the Exterior Communications Interface (ECI), used for coupling with TRACE, was utilized. A Python interface to the ECI library was developed in this work and used to couple an RRS model written in Python to the coupled PARCS/TRACE model. A number of code modifications were made to accommodate the required coupling and correct code deficiencies, with the modified versions named PARCS_Mac and TRACE_Mac. The coupled codes were able to simulate multiple transients based on prior studies as well as operational events. The code updates performed in this work may be used for many future studies, particularly for uncertainty propagation through a full set of calculations, from the lattice model to a full coupled system model.en_US
dc.language.isoenen_US
dc.subjectCANDUen_US
dc.subjectanalysisen_US
dc.subjectsoftwareen_US
dc.subjectSCALEen_US
dc.subjectPolarisen_US
dc.subjectPARCSen_US
dc.subjectTRACEen_US
dc.subjectreactor physicsen_US
dc.subjectthermalhydraulicsen_US
dc.subjectreactor controlen_US
dc.subjectuncertainty analysisen_US
dc.subjectBEPUen_US
dc.subjectsimulationen_US
dc.subjectsafety analysisen_US
dc.subjectnuclearen_US
dc.titleDevelopment and Evaluation of Polaris CANDU Geometry Modelling and of TRACE_Mac/PARCS_Mac Coupling with RRS for CANDU Analysisen_US
dc.title.alternativePolaris and TRACE/PARCS Code Development for CANDU Analysisen_US
dc.typeThesisen_US
dc.contributor.departmentEngineering Physicsen_US
dc.description.degreetypeThesisen_US
dc.description.degreeDoctor of Philosophy (PhD)en_US
dc.description.layabstractModern nuclear safety analysis tools offer more accurate predictions for the safety and operation of nuclear reactors, including CANDU reactors. These codes take advantage of modern computer hardware, and also a shift in philosophy from conservative analysis to best estimate plus uncertainty analysis. The goal of this thesis was to adapt a number of modern tools to support CANDU analysis and uncertainty propagation, with a particular emphasis on coupling of multiple interacting models. These tools were then demonstrated, and results analyzed. The simulations performed in this work were successful in producing results comparable to prior studies along with experimental and operational data. This included the simulation of four weeks of reactor operation including “shim mode” operation. Sensitivity and uncertainty analyses were performed over the course of the work to quantify the precision and significance of the results as well as to identify areas of interest for future research.en_US
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