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Please use this identifier to cite or link to this item: http://hdl.handle.net/11375/28341
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dc.contributor.advisorLuxat, John-
dc.contributor.authorReale Hernandez, Cuauhtemoc-
dc.date.accessioned2023-02-27T18:57:31Z-
dc.date.available2023-02-27T18:57:31Z-
dc.date.issued2023-
dc.identifier.urihttp://hdl.handle.net/11375/28341-
dc.description.abstractIn the recent years there has been growing interest in small modular reactors (SMRs). Before this type of reactors are deployed it is necessary to assess their safety with the newest available tools. This thesis focuses on one SMR, the SEALER reactor, which is a 3 to 10 MWe lead cooled reactor intended for remote communities or mines. The designer of the SEALER reactor has previously identified a possible issue during a loss of flow transient. At the beginning of the transient, the mass flow at the pumps undergoes a fluctuation that could lead to reverse flow if amplified. The first part of the thesis was to perform an uncertainty and sensitivity analysis using an existing lumped-parameter model. Two types of transients were studied: unprotected loss of flow and unprotected overpower. Results show that, for both transients, temperatures remain well below safety limits for the entire parameters space. However, it is also found that reverse flow at the pumps is possible by changing some parameters in a realistic way. It was therefore decided to develop a more realistic model to study the same transients, which constitutes the second and main part of the thesis. The new model uses CFD for simulating the flow of coolant in the entire primary circuit. The complex components (fuel channels, pumps and steam generators) are replaced with a simple geometry and appropriate heat and momentum sources/sinks. The CFD simulation is coupled with a custom-made code for solving heat transfer in the fuel pins and to point kinetics for neutronics. To demonstrate the viability of the model, a validation exercise was performed to ensure that the CFD part is able to reproduce experimental data with important features, like temperature stratification and a jet into a plenum. Results from the new model confirm the mass flow fluctuation if a small pump flywheel is used. For a flywheel of reasonable size, transients are slow without any mass flow fluctuation, and temperature variations are small.en_US
dc.language.isoenen_US
dc.subjectnuclearen_US
dc.subjectCFDen_US
dc.subjectSMRen_US
dc.subjectlead-cooled reactoren_US
dc.subjectsimulationen_US
dc.subjectthermal-hydraulicsen_US
dc.subjecttransienten_US
dc.subjectsensitivity analysisen_US
dc.titleDevelopment of a Multiscale Analysis Methodology for Analysis of Transients in a Small Lead Cooled Advanced Reactoren_US
dc.title.alternativeTRANSIENTS IN A SMALL LEAD COOLED REACTORen_US
dc.typeThesisen_US
dc.contributor.departmentEngineering Physics and Nuclear Engineeringen_US
dc.description.degreetypeThesisen_US
dc.description.degreeDoctor of Philosophy (PhD)en_US
dc.description.layabstractIn the recent years, new types of small nuclear reactors for producing electricity are being developed. The motivation of this thesis is to investigate a particular safety aspect of one of those reactors. One of the main tasks of a nuclear reactor is to transport heat from the core, where the nuclear reaction produces heat, to the component that produces steam which will then activate a turbine to generate electricity. This is achieved by circulating a fluid between those two parts of the reactor with the help of pumps. Any new reactor needs to be designed in a way that if the pumps stop working, no component will overheat and the reactor will shut down safely. This thesis investigates this safety aspect by developing a computer model that can simulate the behavior of the reactor in the case of a loss of pump power. The main takeaway is that the computer model works well and the results from the simulations show that the reactor remains safe in such an accident scenario.en_US
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