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Filtering by: Alternative title ssim SG 2 Remove constraint Alternative title ssim: SG 2 Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian Degree Name Master of Science (M.S.) Remove constraint Degree Name: Master of Science (M.S.)

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  • Comparative analysis of the Žukauskas method and data from the OSU MASLWR test facility steam generator

    Creator:
    Wuth, Bradyn J.
    Abstract:
    Some of the next generation of small modular reactors have been designed with helically coiled steam generators integrated into the reactor vessel to enhance natural circulation. According to the developers of TASS/SMR, a one-dimensional thermal hydraulic code written to model the Korean Atomic Energy Research Institute's SMART reactor, the Žukauskas...
    Resource Type:
    Masters Thesis
    Full Text:
    . . . . . . . . . . . . . . . . . . . . . . . . . 2 1.1.1 NuScale Power, Inc. . . . . . . . . . . . . . . . . . . . . . . . 5 1.1.2 Multi

  • Effects of fluid axial conduction on liquid metal natural circulation and linear stability

    Creator:
    Sabharwall, Piyush
    Abstract:
    The effect of fluid axial thermal conduction on one-dimensional liquid metal natural circulation and its linear stability was performed through non-dimensional analysis, steady-state assessment, and linear perturbation evaluation. The Nyquist criterion and a root search method were employed to find the linear stability boundary of both forward and backward circulations....
    Resource Type:
    Masters Thesis
    Full Text:
    ................................................................... 1 2. STAR-LM............................................................................. 6 2.1

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 1.3 Document Overview . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 2 Literature

  • 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:
    . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 1.4 Thesis Objective and Overview . . . . . . . . . . . . . . . . . . . . . 7 2 Survey of

  • Characterization of fission product transport in a gen. IV gas-cooled fast reactor plant utilizing vented fuel

    Creator:
    Deason, Wesley
    Abstract:
    Fission product transport in a Gen. IV Gas-Cooled Fast Reactor Plant utilizing vented fuel has been characterized using analytical and computational methods. The goal was to increase current understanding of fission product transport in helium-cooled GFRs using vented fuel and to provide a toolset for determining issues which may arise...
    Resource Type:
    Masters Thesis
    Full Text:
    ...................................................................4 2 Literature Review