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Filtering by: Creator French, Kellie M. Remove constraint Creator: French, Kellie M. Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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  • 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

  • Development of a Fast Spectrum Test Loop at the Advanced Test Reactor

    Creator:
    Higgins, Anton
    Abstract:
    The United States currently has no infrastructure to provide a fast neutron flux for research purposes. With the increased interest in Sodium Fast Reactor (SFR) technology, this type of infrastructure is necessary for further development of key components such as Versatile Test Reactor. The purpose of this research is to...
    Resource Type:
    Masters Thesis
    Full Text:
    reactor is a pool type research reactor located in southern France operated by the French Alternative