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  • Heat generation rates of nonfissionable materials in a nuclear reactor environment

    Creator:
    Zimmerman, Paul James
    Abstract:
    Radiation induced heat generation rates of several nonfissionable materials were measured calorimetrically in a nuclear reactor environment. The calorimeter was uniquely designed to allow many materials of grossly different heat generation rates to be measured. heat transfer characteristics of the calorimeter were determined analytically and experimentally. Materials were chosen to...
    Resource Type:
    Masters Thesis
    Full Text:
    materials and, generally, any material placed in a nuclear environment must be known to some degree of

  • Predicting Thermal Conductivity in Nuclear Fuels using Rattlesnake-Based Deterministic Phonon Transport Simulations

    Creator:
    Harter, Jackson R.
    Abstract:
    The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF) formulation is applied to simulate phonon transport. The neutron transport code Rattlesnake is leveraged in this fashion, slightly modi ed to accept input from variables consistent with phonon transport simulations. Several benchmark problems are modeled to assess the potential...
    Resource Type:
    Masters Thesis
    Full Text:
    the reactor core. Characterization of nuclear fuel material properties is an active area of research

  • 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

  • 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:
    the degree of Master of Science in Nuclear Engineering presented on June 11, 2015. Title: Flat Plate

  • Fabric composite radiation heat transfer study

    Creator:
    Gulshan, Zubaida A.
    Abstract:
    A Fabric Composite Radiation Heat Transfer Study has been conducted to determine the effective emissivities of specific fabric composite materials. The weave of the fabric and the high strength capability of the individual fiber in combination with the thermal conductivity and chemical stability of specific metallic liner, result in a...
    Resource Type:
    Masters Thesis
    Full Text:
    material 32 4.2. Comparison of effective emissivities of stainless steel and fabric composite materials

  • Natural Convection Heat Transfer and Boundary Layer Transition for Vertical Heated Cylinders

    Creator:
    Goodrich, Sam S.
    Abstract:
    In recent years, the global nuclear industry has placed a greater emphasis on passively safe reactor designs. In particular, much attention and design work has been applied to engineered systems for passive cooling of nuclear fuel, whether it be loaded in a core or stored in spent fuel pools. The...
    Resource Type:
    Dissertation
    Full Text:
    OF THE DISSERTATION OF Sam S. Goodrich for the degree of Doctor of Philosophy in Nuclear

  • A thermal hydraulics analysis of a molybdenum production element for implementation in TRIGA reactors

    Creator:
    Byfield, Patrick
    Abstract:
    The metastable isotope of technetium-99 (Tc-99m) is an important diagnostic tool used in the field of nuclear medicine due to the isotope's 6.0 hour half-life, 140.5 keV γ-decay mechanism, and multiple oxidation states [1,2]. Approximately 70% of the world’s nuclear medicine procedures involve the use of Tc-99m [3]. The conventional...
    Resource Type:
    Masters Thesis
    Full Text:
    degree of Master of Science in Nuclear Engineering presented on June 7, 2013. Title: A Thermal

  • Scaling analysis of the Direct Reactor Auxiliary Cooling System for Gas-cooled Fast Reactors during a Depressurized Loss of Forced Convection Event

    Creator:
    Blake, Grant C.
    Abstract:
    The Direct Reactor Auxiliary Cooling System (DRACS) is a passive safety system capable of removing decay heat directly from the reactor core. Its modularity makes it scalable for use in reactors with various power levels. Work has previously been completed to support inclusion of the DRACS in liquid metal reactors...
    Resource Type:
    Masters Thesis
    Full Text:
    the degree of Master of Science in Nuclear Engineering presented on September 20, 2016 Title

  • Scaling of the Chinese HTR-PM Reactor Design for Licensing and Testing at the Oregon State University High Temperature Test Facility

    Creator:
    Cox, Jordan
    Abstract:
    The United States (US) Department of Energy (DOE) has identified the pebble-bed reactor as a high priority for US research with the end goal of licensing a pebble-bed reactor (PBR) for operation in the United States. Before this can be accomplished significant research must be done regarding the safety of...
    Resource Type:
    Masters Thesis
    Full Text:
    likelihood of a nuclear accident using fuel design and material properties. To this end this company began

  • Heat transport at interface in the metal-organic-frameworks MOF-5

    Creator:
    Huang, Wenxi
    Abstract:
    The metal-organic–framework MOF-5 is used as an adsorbent in advanced systems for vehicular hydrogen storage that are currently under development. Presently, these systems are limited by poor thermal conductivity of the adsorption bed, and thus our research addresses how the interfaces between grains of MOF-5 can be engineered to improve...
    Resource Type:
    Masters Thesis
    Full Text:
    : Enthalpy of formation and energy landscape of porous materials. Journal of the American Chemical Society