Index Catalog // ScholarsArchive@OSU

A General Purpose Agent-Based Blackboard Optimization Method Applied to Sodium Fast Reactor Design and Analysis

Creator:: Stewart, Ryan H.
Abstract:: We present a novel multi-objective optimization methodology built upon a multi-agent blackboard framework. This multi-agent blackboard system (MABS) synthesizes blackboard architectures, multi-agent environments, and optimization theory. The blackboard architecture creates the framework for initializing, storing, and solving a multi-objective optimization problem. Multiple agents allow for an optimization problem to be...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Ryan H. Stewart for the

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Creator:: Tamashiro, Aaron S.
Abstract:: During the past few decades, the U.S. Department of Energy (DOE) has made significant investments to improve nuclear data libraries, as the quality of this data impacts nearly all analyses of nuclear systems. Nuclear fission product yields are one component of these libraries, and are important for the analysis of...
Resource Type:: Masters Thesis
Full Text:: the Godiva-IV critical assembly in New Mexico in collaboration with Lawrence Livermore National

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:: AN ABSTRACT OF THE THESIS OF Christopher J. Francy for

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Creator:: Brice, Derek J.
Resource Type:: Masters Thesis
Full Text:: storage containers at Trojan Nuclear Power Plant AN ABSTRACT OF THE THESIS OF Derek J. Brice for the

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:: : Camille J. Palmer Todd S. Palmer This thesis presents a feasibility study of a thorium fueled thermal

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:: 1.8 MeV inverse beta decay threshold (Huber, 2004). 1.4 Antineutrino Detectors Lawrence Livermore

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:: first internship experience was at Lawrence Livermore National Laboratory. My mentor, Jonathan A. Walsh

The iterative thermal emission Monte Carlo method for thermal radiative transfer

Creator:: Long, Alex R.
Abstract:: For over 30 years, the Implicit Monte Carlo (IMC) method has been used to solve challenging problems in thermal radiative transfer. These problems are typically optically thick and di ffusive, as a consequence of the high degree of "pseudo-scattering" introduced to model the absorption and reemission of photons from a...
Resource Type:: Masters Thesis
Full Text:: career issues has been invaluable. Nick Gentile, my mentor at Lawrence Livermore National Laboratory

Design and analysis of a nuclear reactor core for innovative small light water reactors

Creator:: Soldatov, Alexey I.
Abstract:: In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
Resource Type:: Dissertation
Full Text:: Dr. Jamie J Kruzic, who have helped me with development of the research concepts and ideas, and

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:: direction of the velocity )I, Projection after i and j axes (i, x, y, z) of ) dQ Unit of the solid angle

ScholarsArchive@OSU

A General Purpose Agent-Based Blackboard Optimization Method Applied to Sodium Fast Reactor Design and Analysis

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Detection of actinides via nuclear isomer de-excitation

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

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

Analysis of the antineutrino rate during CANDU reactor startup

Generation of Multigroup Multiband Cross Sections with Monte Carlo Simulations

The iterative thermal emission Monte Carlo method for thermal radiative transfer

Design and analysis of a nuclear reactor core for innovative small light water reactors

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

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