Index Catalog // ScholarsArchive@OSU

The Control and Safety Analysis of a Small Fission Surface Power Reactor

Creator:: Nelson, Noel B.
Abstract:: The NKUA1 is a Small Fission Surface Power (SFSP) space reactor intended for use in upcoming missions to Mars and the moon between the years 2020-2030. The concept of the reactor was created by Dr. Lee Mason and his research team in a joint effort between the Department of Energy...
Resource Type:: Honors College Thesis
Full Text:: Health Physics Dean, University Honors College I understand that my

Assessing Several Modeling Approaches in Depletion Studies of a TRISO-Fueled Microreactor

Creator:: Hoffman, Keenan J.
Abstract:: The impact of MCNP6 depletion resolution on core lifetime is examined in the context of the Snowflake microreactor with explicit TRISO fuel. The change in core lifetime and iso- tope mass as a result of different tracked isotopes, timesteps, and spatial regions is discussed. Calculation speed of a prototype MCNP...
Resource Type:: Masters Thesis
Full Text:: Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

Creator:: Misner, Alex C.
Abstract:: Antineutrino detectors could provide a valuable addition to current safeguards regimes. Antineutrinos are an attractive emission to monitor due to their low interaction cross-section that prevents them from being shielded and the dependence of their spectrum on the power level and isotopic content of a reactor core. While there are...
Resource Type:: Dissertation
Full Text:: _____________________________________________________________________ Dean of the Graduate School I understand that my dissertation will become part of the

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

Radioxenon generation using highly enriched uranium

Creator:: Elliott, Anthony James
Abstract:: This work focuses on the generation and collection of four specific radioxenon isotopes; xenon-131m, xenon-133m, xenon-133 and xenon-135. These nuclides are created by fissioning a highly enriched uranium sample using a thermal neutron source from a university research reactor. The three main aspects of this work include: (1) Conducting preliminary...
Resource Type:: Masters Thesis
Full Text:: Engineering and Radiation Health Physics Dean of the Graduate School I understand

Assessing the Quality of Three Dimensional Simplified Spherical Harmonic (SPN) Radiation Transport Solutions to Source Detector Problems

Creator:: Patel, Japan K.
Abstract:: The research objective is to assess the performance of the SPN transport method, with a traditional finite volume spatial discretization in Cartesian geometry, on source detector problems relevant to urban detonation of an improvised nuclear device. In particular, we observe the character of the solution as a function of the...
Resource Type:: Honors College Thesis
Full Text:: ______________________________________________________________________ Dean, University Honors College I understand that my project will become part of the

Data driven study of neutron response in Minerva using quasielastic neutrino scattering

Creator:: Peters, Evan
Abstract:: Understanding how particles behave in detectors is a critical part of analyzing data from neutrino experiments. There are methods in place to track charged particles in scintillator material, but neutral particles such as neutrons are more difficult to characterize. The purpose of this project was to assess and calibrate methods...
Resource Type:: Honors College Thesis
Full Text:: Science and Engineering Toni Doolen, Dean, Oregon State University Honors College I understand that my

A comparative study of nodal course-mesh methods for pressurized water reactors

Creator:: Bukar, Kyari Abba
Abstract:: Several computer codes based on one and two-group diffusion theory models were developed for SHUFFLE. The programs were developed to calculate power distributions in a two-dimensional quarter core geometry of a pressurized power reactor. The various coarse-mesh numerical computations for the power calculations yield the following: the Borresen's scheme applied...
Resource Type:: Masters Thesis
Full Text:: Redacted for Privacy _____& p,Head of Deartment of Nuclear engineering Redacted for Privacy Dean of

Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

Creator:: Hummel, Andrew J.
Abstract:: The most widely used and versatile medical radioisotope today is technetium-99m. Roughly 30 million people depend on this radioisotope for diagnostic procedures each year, and this demand is expected to grow. Although there are numerous ways of procuring this isotope, the most common and most practical, for reasons to be...
Resource Type:: Dissertation
Full Text:: Head of the Department of Nuclear Engineering and Radiation Health Physics Dean of the

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

Creator:: Kumar, Ravi
Abstract:: In this thesis, we expand the scope of a previously introduced Artificial Neural Network (ANN) method to solve the slab-geometry discrete ordinates (S$_N$) neutron transport equations. Specifically, we extend the method to energy-dependent (multi-group) fixed source problems involving heterogeneous media and more general boundary conditions - vacuum and incident flux...
Resource Type:: Masters Thesis
Full Text:: Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

ScholarsArchive@OSU

The Control and Safety Analysis of a Small Fission Surface Power Reactor

Assessing Several Modeling Approaches in Depletion Studies of a TRISO-Fueled Microreactor

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

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

Radioxenon generation using highly enriched uranium

Assessing the Quality of Three Dimensional Simplified Spherical Harmonic (SPN) Radiation Transport Solutions to Source Detector Problems

Data driven study of neutron response in Minerva using quasielastic neutrino scattering

A comparative study of nodal course-mesh methods for pressurized water reactors

Molybdenum-99 production in the Oregon State TRIGA reactor : analysis of the reactor design using a new LEU target as fuel

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

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