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Filtering by: Alternative title ssim Internal report no. 125 Remove constraint Alternative title ssim: Internal report no. 125 Academic Affiliation Nuclear Science and Engineering Remove constraint Academic Affiliation: Nuclear Science and Engineering Committee Member Minc, Leah Remove constraint Committee Member: Minc, Leah

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  • Locating and Quantifying Contamination Deposited in Radiation Puncture Wounds

    Creator:
    Wehmann, Nicholas K.
    Abstract:
    Internal dosimetry models show a representation of how radionuclides move through the body. This study takes a look at radiation wounds by modelling a puncture wound to the hand using Microshield software. An analysis of these models provides a triangulation method that could be used to investigate wound characteristics, as...
    Resource Type:
    Masters Thesis
    Full Text:
    ), published Report No. 156. This report contained a compartment model for internal dosimetry following the

  • 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

  • Butterfly Puddling: An Alternative Cs-137 Pathway to the Pale Grass Blue Butterfly Following the Fukushima Nuclear Accident

    Creator:
    Hermann, David A.
    Abstract:
    Environmental modeling as a result of the Fukushima accident has been at the forefront for present day health physics. The accident released radionuclides in the environment and the fate and transport of these radionuclides are of interest when considering doses to non-human biota. The Pale Grass Blue Butterfly was studied...
    Resource Type:
    Masters Thesis
    Full Text:
    Complexities……………………………………….….39 3 Materials & Methods.……….…………………..…...…………………………………………47 3.1 Internal

  • 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

  • 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

  • Comparison of Attila SN Particle Transport Code with MCNP in the Analysis of Small Modular Reactor Shielding

    Creator:
    Rose, Charlotte
    Abstract:
    Of great importance in the design of a nuclear power plant is the evaluation of shielding from the ionizing radiation produced in the core of the nuclear reactor. This requires simulation software to predict the dose rates in the areas of interest. Comparing the simulation of the same modeled system...
    Resource Type:
    Masters Thesis
    Full Text:
    ........................................................ 42 Figure 10 Custom Report Selection in Attila GUI

  • 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