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Filtering by: Creator Kelley, Brian F. Remove constraint Creator: Kelley, Brian F. Advisor Palmer, Todd S. Remove constraint Advisor: Palmer, Todd S.

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  • 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:
    the absorption-reemission process through a scattering event. When the Fleck factor is small (i.e., f

  • Modeling the Oregon State University TRIGA Reactor Using the Attila Three-Dimensional Deterministic Transport Code

    Creator:
    Keller, S. Todd
    Abstract:
    Attila is a state-of-the-art radiation transport based code that is efficient, accurate and straightforward to use. Geometric information is input to the code as CAD drawings. Material property information is input as a cross section library. The user has full control over standard transport options and output reports. In phase...
    Resource Type:
    Masters Thesis
    Full Text:
    possible. Thanks as well to my committee members, Dr. Brian Woods of the Nuclear Engineering and

  • Feasibility Study of a Thermal Spectrum Thorium Breeder Reactor Without Chemical Reprocessing

    Creator:
    Keppen, Jackson D.
    Abstract:
    This thesis presents a feasibility study of a thorium fueled thermal spectrum breeder-burner reactor that operates without chemical reprocessing. Materials were evaluated for their potential as moderators using standard analytical methods. These materials were then used as moderators to evaluate criticality and enrichment in an infinite fuel pin lattice. The...
    Resource Type:
    Masters Thesis
    Full Text:
    ; • f is the thermal utilization, which is the probability that an absorbed thermal neutron is absorbed

  • Predicting antineutrino source terms from a high temperature gas reactor

    Creator:
    Shaughnessy, Andra L.
    Abstract:
    Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors and are able to determine power levels and burn up throughout a fuel cycle. This technology could allow the IAEA to monitor LWRs remotely and...
    Resource Type:
    Masters Thesis
    Full Text:
    Brian: I would not have made it through all those classes without your hours of explanation. Thanks so

  • Feasibility Study of Using HANARO Fuel Rods in WWR-SM Reactor

    Creator:
    Peguero, Lara M.
    Abstract:
    Interest in increased fuel supply stability has driven an investigation into possible alternate fuel for use in the WWR-SM research reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research reactor currently utilizing IRT-4M fuel made by a single Russian supplier. A candidate for...
    Resource Type:
    Masters Thesis
    Full Text:
    . F = φσN (2.5) Power density is an indication of how the power in a reactor core is distributed

  • 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:
    . My parents, James F. Reynolds and Jana A. H. Reynolds, have provided con- stant support for my

  • Reduced Order Modeling of Radiation Diffusion Kinetics via Proper Generalized Decomposition

    Creator:
    Alberti, Anthony L.
    Abstract:
    In this dissertation, we attempt to overcome the "curse of dimensionality" inherent to radiation diffusion kinetics problems by employing a novel reduced order modeling technique known as proper generalized decomposition (PGD). After verifying a proposed PGD algorithm and associated solvers through various tests, we explore its performance for computing reduced-order...
    Resource Type:
    Dissertation
    Full Text:
    differential equation, α ∂u ∂t −∇ · κ∇u = f(r, t). (2.1) Without loss of generality, we can apply an

  • Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems

    Creator:
    Somasundaram, Elanchezhian
    Abstract:
    The implementation of advanced hybrid (Monte Carlo/Deterministic) transport methods for realistic test problems has been a challenge due to the overhead efforts associated with interfacing a solution generated by a deterministic solver with a Monte Carlo based radiation transport code. In this work, with the help of Transpire, Inc., a...
    Resource Type:
    Dissertation
    Full Text:
    . Brian Woods, professor Dr. Leah Minc and my minor professor, Dr. Lisa J. Madsen for serving as my

  • Analysis of the method of tubes characteristic schemes in the thick diffusive limit

    Creator:
    Rising, Michael E.
    Abstract:
    Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport problems. These methods are most often used for neutron transport applications (i.e. lattice physics calculations) where spatial cells are of intermediate optical thickness (O(1) - O(100) mean free paths, depending on the energy group)...
    Resource Type:
    Masters Thesis
    Full Text:
    years. I would like to thank the remaining members of my thesis committee, Dr. Brian Woods from the

  • Generation of Multigroup Multiband Cross Sections with Monte Carlo Simulations

    Creator:
    Lam, Adam Q.
    Abstract:
    This is the investigation into The generation of high-fidelity multigroup multiband cross sections from Monte Carlo neutron transport simulations. Previous methods for generating multigroup multiband (MGMB) cross sections, and multigroup cross sections, assume an approximate shape for the scalar flux. This approximate flux shape is the product of an energy-dependent...
    Resource Type:
    Masters Thesis