Search Constraints

Start Over
Filtering by: Creator Erhard, Dean Hamilton Remove constraint Creator: Erhard, Dean Hamilton Advisor Palmer, Todd S. Remove constraint Advisor: Palmer, Todd S. Degree Name Master of Science (M.S.) Remove constraint Degree Name: Master of Science (M.S.)

Search Results

  • Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios

    Creator:
    Somasundaram, Elanchezhian
    Abstract:
    Detection of reactor antineutrinos for non-proliferation applications has been researched extensively across the globe and is considered as a potential technology to remotely monitor reactor operations without any intrusions to reactor components. Reactor antineutrino detection experiments have been conducted in the past and have proven successful in detecting the changes...
    Resource Type:
    Masters Thesis
    Full Text:
    _____________________________________________________________________ Dean of the Graduate School I understand that my thesis will become part of the

  • Analysis of the antineutrino rate during CANDU reactor startup

    Creator:
    Matthews, Christopher
    Abstract:
    Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to visual inspections and intrusive monitoring systems. The recent development of antineutrino detectors may soon allow real-time monitoring from an unobtrusive location. Antineutrinos are produced through...
    Resource Type:
    Masters Thesis
    Full Text:
    _____________________________________________________________________ Dean of the Graduate School I understand that my thesis will become part of the

  • Detection of actinides via nuclear isomer de-excitation

    Creator:
    Francy, Christopher J.
    Abstract:
    The detection of illicit weapons-grade nuclear material is a significant technical challenge receiving a great deal of attention in the nuclear community. A proposed solution is to actively bombard the material under investigation with neutrons, populating nuclear isomers in any potential fissile material. These isomers decay quickly, releasing gamma rays...
    Resource Type:
    Masters Thesis
    Full Text:
    of the Department of Nuclear Engineering and Radiation Health Physics Dean of 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
    Full Text:
    Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

  • High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

    Creator:
    Woods, Douglas N.
    Abstract:
    The high-order finite element S[subscript N] transport equations are solved on several test problems to investigate the behavior of the discretization method on meshes with curved edges in X-Y geometry. Simpler problems ensured the correct implementation of MFEM, the general fi nite element library employed. A convergence study using the...
    Resource Type:
    Masters Thesis
    Full Text:
    Nuclear Science and Engineering Dean of the Graduate School I understand that my thesis will become part

  • Steady State Modeling of the Minimum Critical Core of the Transient Reactor Test Facility

    Creator:
    Alberti, Anthony L.
    Abstract:
    With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
    Resource Type:
    Masters Thesis
    Full Text:
    , representing Nuclear Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate

  • An advanced nodal discretization for the quasi-diffusion low-order equations

    Creator:
    Nes, Razvan
    Abstract:
    The subject of this thesis is the development of a nodal discretization of the low-order quasi-diffusion (QDLO) equations for global reactor core calculations. The advantage of quasi-diffusion (QD) is that it is able to capture transport effects at the surface between unlike fuel assemblies better than the diffusion approximation. We...
    Resource Type:
    Masters Thesis
    Full Text:
    Engineering Head of Department of Nuclear Engineering Dean of Gi4uaie School I understand that my thesis

  • Pair production treatments for deterministic pulse-height distribution simulations

    Creator:
    MacQuigg, Michael R.
    Abstract:
    This thesis presents methods for treating annihilation photon pairs in deterministic pulse height distribution (PHD) simulations. The methods are applied in PHD simulations for monoenergtic sources of 1.6 and 2.6 MeV photons incident on 5 and 10 cm 1-D slabs of germanium, sodium iodide, and lead and the results are...
    Resource Type:
    Masters Thesis
    Full Text:
    Radiation Health Physics Dean of the Graduate School I understand that my thesis will become part of the

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

  • An assessment of a mesh-based method for slab-geometry transport in stochastic materials

    Creator:
    Bassett, Brody R.
    Abstract:
    There exists a variety of methods to solve the radiation transport equation in stochastic materials, including the Levermore-Pomraning method and the atomic mix method, each of which is designed to replicate the results given by benchmarks with materials rearranged in a randomized fashion. While the atomic mix method is very...
    Resource Type:
    Masters Thesis
    Full Text:
    Radiation Health Physics Dean of the Graduate School I understand that my thesis will become part of the