Application of High Fidelity Methods to Nuclear Engineering Thermal-Hydraulics Problems
Open Access Depositedidentification of critical impediments to application of non-uniform Fast Fourier Transform based Poisson solvers
The design and safety analysis of nuclear reactors are increasingly challenged by multiscale, transient thermal-hydraulic phenomena that exceed the capabilities of traditional semi-empirical system codes. This dissertation advances direct numerical simulation as a credible and indispensable “numerical laboratory” capable of resolving these complexities. By systematically addressing foundational barriers of software maintainability, numerical scalability, and the resolution of sub-grid physics, this work establishes a high-fidelity pathway for evaluating safety margins in both design-basis and severe accident scenarios. The research is organized around four primary contributions
refactoring legacy simulation frameworks into a modern, maintainable architecture
characterization of transient heat transfer in molten pool convection
and development of a mechanistic sub-turbulence closure for the nucleate boiling ebullition cycle. A key finding includes the discovery that internally heated molten pools, representative of core debris, appear not to exhibit the transient heat transfer overshoots and hysteresis seen in canonical boundary-heated systems, suggesting a greater resilience in current safety correlations. By bridging the gap between fundamental fluid dynamics and engineering-scale safety challenges, this work demonstrates the physical insights that are gained from resolving the smallest scales of turbulence and heat transfer are invaluable.
- All rights reserved
Notice to Authors
If you are the author of this work and you have any questions about the information on this page, please use the Contact form to get in touch with us.