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Filtering by: Alternative title ssim Internal report no. 125 Remove constraint Alternative title ssim: Internal report no. 125 Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah Degree Field Nuclear Engineering Remove constraint Degree Field: Nuclear Engineering

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  • 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:
    States currently has no infrastructure to provide a fast neutron flux for research purposes. With the

  • Study on Depressurized Loss of Coolant Accident and its Mitigation Method Framework at Very High Temperature Gas Cooled Reactor

    Creator:
    Gutowska, Izabela
    Abstract:
    To understand how a Depressurized Loss of Forced Convection (D-LOFC) initiated from a double-ended guillotine break may affect further operation of a High Temperature Gas Cooled Rector (HTGR), thorough understanding of each specific stage of this event is required. Key considerations that need to be determined is the amount of...
    Resource Type:
    Dissertation
    Full Text:
    from [25] with no changes

  • 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

  • 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:
    ............................................................... 106 Table 5-2 Core Region Internal Thermal Conductor Types ..................................... 116

  • Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

    Creator:
    Mai, Anh T.
    Abstract:
    The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
    Resource Type:
    Masters Thesis
    Full Text:
    ................................................................................................................ 114 A APPENDIX (4.25 % Enriched Fuel, No BP Core Results

  • 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

  • Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

    Creator:
    Woods, Douglas N.
    Abstract:
    We spatially discretize the Sn transport equation using the high-order (HO) discontinuous finite element method (DFEM) on HO meshes. Previous work provided a proof-of-concept for this spatial discretization method in X-Y geometry. Included in the present work, we derive a spatial discretization for the Sn transport equation in both X-Y...
    Resource Type:
    Dissertation
    Full Text:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 125 79 Spectral radius data for varying p with C = 2 on an orthogonal mesh with homogeneous

  • 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:
    , no theoretical model has been made to describe the HSN process. The reason of the transition from

  • Development of a Novel MEMS Thermal Sensor Array for Pebble Bed HTGRs

    Creator:
    Hertel, Matthew A.
    Abstract:
    A novel high temperature thermal instrument is proposed, which utilizes a dual-sensing platinum resistor encased in a mono-crystalline alpha-alumina (sapphire) substrate. The instrument is comprised of four platinum trace elements, oriented with 90° rotational symmetry atop a 1120 oriented crystal lattice substrate. All four of these sensors measure temperature directly...
    Resource Type:
    Dissertation
    Full Text:
    of gratitude. No difficult task is accomplished alone, no man is an island, and this achievement