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Filtering by: Has journal Wood Material Science & Engineering Remove constraint Has journal: Wood Material Science & Engineering Committee Member Woods, Brian Remove constraint Committee Member: Woods, Brian Decade 2020-2029 Remove constraint Decade: 2020-2029

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  • Design of a Pebble Bed Separate Effects Test for Molten Salt Reactors

    Creator:
    Uselman, Jacob S.
    Abstract:
    The licensing of novel nuclear reactor power plant designs requires extensive research and testing. A significant portion of this work is dedicated to the design and operation of scaled-down testing facilities that emulate various plant conditions. The data gathered from these test facilities is used to compare to predictive models....
    Resource Type:
    Masters Thesis
    Full Text:
    Master of Science in Nuclear Engineering presented on September 3, 2020. Title: Design of a

  • Development of a Rapid Power Transient Critical Heat Flux Model

    Creator:
    Brown, Emory G.
    Abstract:
    The understanding of critical heat flux is crucial for the safety of nuclear reactors. To this end, many studies have been carried out to understand various aspects of the boiling crisis phenomenon. Power transient critical heat flux trigger mechanisms is a small category that is relatively under-studied and not well...
    Resource Type:
    Dissertation
    Full Text:
    , representing Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

  • Heat Transfer Coefficient Correlation Development of Dowtherm A in the Near Wall Region of a Pebble Bed Reactor

    Creator:
    Dionne, Connor J.
    Abstract:
    Computational fluid dynamics conjugate heat transfer simulations were performed on a packed bed test facility using Dowtherm-A as the working fluid. Multiple test cases were simulated for a Reynolds number range of 188 – 1524 and a set heater power of 60 kW. Temperature profiles were extracted, and the near-wall...
    Resource Type:
    Masters Thesis
    Full Text:
    for the degree of Master of Science in Nuclear Engineering presented on June 3, 2021. Title

  • Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

    Creator:
    Lam, Adam Q.
    Abstract:
    In this dissertation, we derive and implement a new transport-diffusion hybrid algorithm for solving thermal radiative transfer (TRT) problems. Using the method of nonlinear elimination (NLEM), the TRT system of equations can be written in terms of a transport equation with the absence of scattering and a diffusion equation. The...
    Resource Type:
    Dissertation
    Full Text:
    Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand that

  • A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

    Creator:
    Reynolds, Aaron J.
    Abstract:
    Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor (DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other reactor types. This environment can be computationally challenging to model, given that the multiphysics phenomena generally have non-linear interdependencies requiring the use of iterative solution...
    Resource Type:
    Dissertation
    Full Text:
    Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

  • 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:
    , representing Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

  • 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
    Full Text:
    Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

  • Experimental Study of the Impact of Physical and Chemical Properties on Smoldering Combustion in Natural Fuels

    Creator:
    Smucker, Benjamin
    Abstract:
    Smoldering combustion in wildland fires is difficult to extinguish, can transition to flaming combustion, and produces a significant amount of pollutants. It is necessary to understand parameters controlling smoldering in order to help predict the smoldering behavior and potentially mitigate these hazards. The wide variety of natural fuels that occur...
    Resource Type:
    Dissertation
    Full Text:
    Smucker for the degree of Doctor of Philosophy in Mechanical Engineering presented on June 22, 2023