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Development of Reactor System Code Analysis Workbook: RELAP5/ASYST

dc.contributor.advisorNOVOG, David
dc.contributor.authorBELLO, Solomon
dc.contributor.departmentEngineering Physicsen_US
dc.date.accessioned2024-08-26T18:59:20Z
dc.date.available2024-08-26T18:59:20Z
dc.date.issued2024
dc.descriptionA comprehensive workbook with case samples for RELAP5 and ASYST usersen_US
dc.description.abstractAbstract In the operation of nuclear reactor, proficient utilization of system code analysis tools in predicting reactor behaviour is critical for ensuring safe operation and performance optimization. However, the complexity inherent in these tools often poses a significant challenge for new users, hindering their ability to navigate and utilize these systems effectively. This workbook aims to address this challenge by presenting a comprehensive training package specifically designed for new users delving into system code analysis. It provides consistent examples, analytical solutions and results for two major nuclear reactor system codes (RELAP5 and ASYST), different models, and analysis techniques into a single, user-friendly platform. The overarching objective is to provide prospective nuclear engineers, researchers, and operators with a versatile and efficient tool that streamlines the process of initial training for reactor system analysis. This work provides the much needed structured and accessible training methodologies to facilitate skill acquisition among new users in nuclear power engineering. The methodology employed involves description of basic required components, theoretical background, and simulation results. Essential components of this training package include the procedural steps, input file development, practical hands-on exercises and simulated flow cases of reactor components with analytical validation. Each example provides detailed inputs for modelling steady and transient conditions for both single, multi-channels, connecting components and systems. The results of simulations were validated by presenting respective analytical calculations which show good agreement. Sensitivity studies are also included so new users can begin gaining intuition on the impact of some of the inputs of simulation results. Finally, conclusions and recommendations for future work are included in the final chapter.en_US
dc.description.degreeMaster of Applied Science (MASc)en_US
dc.description.degreetypeThesisen_US
dc.description.layabstractThis project aims to develop a initial training workbook for the use of RELAP5 and ASYST system codes in safety analysis. RELAP and ASYST are powerful tools used for simulating the behavior of complex thermal-hydraulic systems, particularly in nuclear power plants. But despite its widespread use in academia and industry, these codes can be challenging for new users due to their complex nature and the multitude of input options. The workbook will serve as a guide for users as it provides step-by-step instructions on problem modeling, components descriptions and nodalizations, input file development, and results analysis. Examples and analytical validation to enhance new users’ understanding of the relationship of the simulations to the theoretical solutions are also included. The development of the workbook stemmed from the recognition of the need for accessible and structured educational resources for RELAP5 and ASYST.en_US
dc.identifier.urihttp://hdl.handle.net/11375/30086
dc.language.isoenen_US
dc.subjectRELAP5en_US
dc.subjectASYSTen_US
dc.subjectCANDU Fuel Bundleen_US
dc.subjectReactor Codes Workbooken_US
dc.subjectHeat Structureen_US
dc.subjectHeat Exchangeren_US
dc.subjectPumpen_US
dc.subjectLoopen_US
dc.titleDevelopment of Reactor System Code Analysis Workbook: RELAP5/ASYSTen_US
dc.typeThesisen_US

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