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Filtering by: Creator French, Kellie M. Committee Member Minc, Leah Committee Member Marcum, Wade

Computational Fluid Dynamics Benchmark Analysis of an Historical Sodium Loop Experiment

Creator:

Moore, Thomas M.

Abstract:

Sodium cooled nuclear reactors are being considered for the next generation of nuclear power plants to provide clean electricity to the world. To prove the safety of these reactors, the fuel must be shown to safely handle large neutron fluxes that cause a spike in the thermal output of the...

Resource Type:

Masters Thesis

Full Text:

entail. Finally, I would like to graciously thank my darling Kellie Wall in supporting me through this
Analysis of Asymmetric Heating on a Scaled High Temperature Gas Reactor Experiment During a Pressurized Conduction Cooldown

Creator:

Moore, Thomas

Abstract:

Among the candidates for the next generation of nuclear power plant is the high temperature gas reactor (HTGR). Since the HTGR does not have the same operational history as water cooled reactors do in the United States, investigation into the response of different accident phenomena is still an active area...

Resource Type:

Dissertation

Full Text:

have made this task even more worthwhile. Finally, I would like to thank my partner, Kellie. Without
Heat Loss Characterization of NIST-1's Containment Vessel

Creator:

Yoshiura, Ramon K.

Abstract:

NuScale Power has designed a small modular reactor using natural circulation cooling dependent systems for both steady-state and transient operations. The NuScale Integral Test System (NIST-1) facility was built to supply test data to NuScale Power to verify and validate computer codes for the NuScale Power Mod- ule (NPM) with...

Resource Type:

Masters Thesis

Full Text:

Fraction ā Time Averaged Undetermined Fluid Property ṁ ′′′ ij Mass Transfer Rate per Volume from one