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Filtering by: Alternative title ssim Internal report no. 125 Remove constraint Alternative title ssim: Internal report no. 125 Advisor Wu, Qiao Remove constraint Advisor: Wu, Qiao Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah

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  • Flat Plate Free Convective Heat Transfer

    Creator:
    Bristol, Benjanmin R.
    Abstract:
    The OSU MASLWR Test facility is a scaled integral systems LOCA and proof-of-concept test facility for the Multi-Application Small Light Water Reactor design concept. A unique feature of this design is to utilize a small high pressure containment vessel to provide the safety containment function for an integral reactor pressure...
    Resource Type:
    Masters Thesis
    Full Text:
    example of this is the IPWR designs that use internal control 5 Figure 1.1: Westinghouse IRIS PWR

  • A Theoretical Model for Spherical Cap Bubble Geometry

    Creator:
    Wieland, Isaiah T.
    Abstract:
    The significant variation in bubble geometry, as a function of size, has fascinated scientists for hundreds of years. However, a comprehensive explanation for these observations and the underlying physics has eluded researchers. A theoretical model which describes a the relationship between forces that produce spherical cap bubble geometry has been...
    Resource Type:
    Masters Thesis
    Full Text:
    Ratio and Scale Factor . . . . . . . . . . . . . . . . . 125 6.2.56 SF Corrected Bubble Velocities

  • Investigation of Drag Coefficient and Virtual Mass Coefficient on Rising Ellipsoidal Bubbles

    Creator:
    Dueñas, Alexander M.
    Abstract:
    Accurately describing drag and virtual mass forces in two-phase flows is crucial for high fidelity modeling of nuclear thermal hydraulic safety systems. This study compares existing drag coefficient correlations commonly used in computational fluid dynamics (CFD) applications for air bubbles to experimental data collected for ellipsoidal air bubbles of varying...
    Resource Type:
    Masters Thesis
    Full Text:
    . Carl Stoots, who is no longer with us, for being a wonderful person and mentor. He is deeply missed

  • 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:
    , the simulation would be no longer an approximation but a validation processes in CFD terms. 7

  • Gravity-based non-invasive superconducting gravimeter system for reactor coolant inventory monitoring

    Creator:
    Danielson, Jordan J.
    Abstract:
    All nuclear reactors rely heavily on the use of level sensing instrumentation to detect the behaviour of liquid in vessels. The majority of level sensing instruments are differential pressure sensing meters, which are invasive and could be the failure source in the pressure boundary of the primary coolant system. In...
    Resource Type:
    Masters Thesis
    Full Text:
    eliminated. This is advantageous because the primary system no longer has to rely on electricity being