Search Constraints

Start Over
Filtering by: Creator French, Rod A. Remove constraint Creator: French, Rod A. Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah

Search Results

  • 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:
    a lower rod thermal power than expected. A parametric study was also conducted to characterize

  • On the mechanism transition of power transient critical heat flux

    Creator:
    Yan, Yikuan
    Abstract:
    The reactivity-initiated accident (RIA) accident has stirred wide interest for the need of designing advanced and high tolerance fuels for next generation nuclear power plants. For pressurized water reactors (PWRs), the accidentally induced reactivity pulse adds transient energy input to the fuel. As a result, boiling may happen locally. Boiling...
    Resource Type:
    Dissertation
    Full Text:
    power plant by an ejected control rod while at power. When the control rod is ejected in an LWR, a

  • Irradiation Capsule Development for Composite Fuels for Nuclear Thermal Propulsion

    Creator:
    Thody, Austin
    Abstract:
    Nuclear Thermal Rocket (NTR) designs have received renewed interest due to their superior thermal efficiencies and a rehabilitated desire for space exploration. This has resulted in improved NTR fuel designs that have unique properties that require investigation and testing in order to be more safely designed and operated. Oak Ridge...
    Resource Type:
    Masters Thesis
    Full Text:
    and a renewed desire for space exploration. This has resulted in improved NTR fuel designs that have

  • 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:
    it is called ‘NEPTUNE CFD’, a French CFD program co-developed by Electricité de France and