Index Catalog // ScholarsArchive@OSU

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

Creator:: Lilley, Benjamin C.
Abstract:: Material testing experiments are needed to enable the next generation of nuclear fission reactors. Concluding in 2009, the Boosted Fast Flux Loop (BFFL) project was devised as a way to test fast reactor materials and fuels in the Advanced Test Reactor (ATR), however the experiment location it used is now...
Resource Type:: Masters Thesis
Full Text:: of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

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:: been researched extensively across the globe and is considered as a potential technology to

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:: reactor at the Institute of Nuclear Physics in Uzbekistan. The WWR-SM is a high-power, pool-type research

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:: -ray branching ratio data impacts inventory calculation of isotopes. At present, a number of fission

Applying Machine Learning Algorithms to Identify Problematic Nuclear Data within Nuclear Transport Simulations

Creator:: Grechanuk, Pavel A.
Abstract:: The primary goal of this dissertation is to improve the quality of nuclear data available to the nuclear science community. We propose to accomplish this by applying machine learning algorithms to the large number of available benchmark experiments and simulations, with the goal of determining which nuclear data have strong...
Resource Type:: Dissertation
Full Text:: AN ABSTRACT OF THE DISSERTATION OF Pavel A. Grechanuk for

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:: element library employed. A convergence study using the method of manufactured solutions demonstrates the

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:: high-order (HO) dis- continuous finite element method (DFEM) on HO meshes. Previous work provided a

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:: a Mesh-Based Method for Slab-Geometry Transport in Stochastic Materials Abstract approved: Todd S

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:: degree of Doctor of Philosophy in Nuclear Engineering presented on May 20, 2021. Title: A General

Advanced Deterministic Phonon Transport Techniques for Predicting Spectral Thermal Conductivity in Homogeneous and Heterogeneous Media

Creator:: Harter, Jackson R.
Abstract:: We present a deterministic spectral method to predict equilibrium temperature distributions, heat flux, and thermal conductivity in homogeneous and heterogeneous media. We solve the Boltzmann transport equation in a second order spatial, self-adjoint angular flux formulation. We implemented this method into the radiation transport code Rattlesnake, built using the MOOSE...
Resource Type:: Dissertation
Full Text:: encounter at a Steven Wilson concert and seeing your air guitar in action, or your critical reviews of my

ScholarsArchive@OSU

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

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

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

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

Applying Machine Learning Algorithms to Identify Problematic Nuclear Data within Nuclear Transport Simulations

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

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

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

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

Advanced Deterministic Phonon Transport Techniques for Predicting Spectral Thermal Conductivity in Homogeneous and Heterogeneous Media

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

Contributor

Date

Decade

Degree Field

Degree Level

Degree Name

Language

License

Non-Academic Affiliation

Peer Reviewed

Resource Type

Rights Statement

Subject

Search Constraints

Search Results

Limit your search