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  • Feasibility Study on MHD Energy Conversion for Applications in Liquid Metal Cooled Nuclear Reactors

    Creator:
    Qiu, Hanrui
    Abstract:
    The application of two-phase magnetohydrodynamic(MHD) in liquid metal cooled nuclear reactors presents opportunities to simplify the power generation system by eliminating moving components like a turbine for enhanced safety. The proposed system in this thesis consists of two loops with immiscible working fluids. The compressed gas expands in the two-phase...
    Resource Type:
    Masters Thesis
    Full Text:
    ) γ γ−1 e∆s/R (3.7) e∆s/R is the loss term, for the isentropic process ∆s = 0 and for the general

  • 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:
    AN ABSTRACT OF THE THESIS OF Benjanmin R. Bristol for

  • 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:
    Abstract approved: _____________________________________________________________________ Qiao Wu Wade R

  • High pressure condensation heat transfer in the evacuated containment of a small modular reactor

    Creator:
    Casey, Jason R.
    Abstract:
    At Oregon State University the Multi-Application Small Light Water Reactor (MASLWR) integral effects testing facility is being prepared for safety analysis matrix testing in support of the NuScale Power Inc. (NSP) design certification progress. The facility will be used to simulate design basis accident performance of the reactor's safety systems....
    Resource Type:
    Masters Thesis
    Full Text:
                                                                                                                                                                                                                                                                                                                                                                                      AN ABSTRACT OF THE THESIS OF Jason R. Casey for the degree of Master of Science in Nuclear

  • 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:
    . . . . . . . . . . . . . . . . . . . . 144 LIST OF NOMENCLATURE Symbols A Area D, d Diameter g Gravity L Length Scale P Pressure R

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 3.3 Simulation Sensitivity to Changing Number of Points Along R-Axis 40 3.4 Simulation

  • 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:
    ) Pi Partial Vapor Pressure (Pa or kg/m·s2) q ′′ Heat Flux (W/m2) r Grid Refinement Factor Sα Volume

  • Dynamic System Scaling Application to Accelerated Nuclear Fuel Testing

    Creator:
    Yoshiura, Ramon K.
    Abstract:
    The development of nuclear fuel and materials requires is a continuous effort to investigate the acute and prolonged effects of irradiation, thermal-material stress, chemical change, or other conceivable damage mechanics acquired during normal operation or accident scenarios throughout its lifetime. As in-core fuel property measurement techniques advance to support in...
    Resource Type:
    Dissertation