Index Catalog // ScholarsArchive@OSU

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:: ABSTRACT OF THE THESIS OF S. Todd Keller for the degree of Master of Science in Nuclear Engineering

The physical properties, consolidation behavior, and stability of the sediments of the Peru-Chile continental margin

Creator:: Busch, William H.
Resource Type:: Dissertation
Full Text:: : / George H. Keller Coastal upwelling markedly influences sediment physical properties along the Peru

Influence of organic matter on the geotechnical properties and consolidation characteristics of northern Oregon continental slope sediments

Creator:: McDonald, William P.
Resource Type:: Masters Thesis
Full Text:: gratefully acknowledge the support of my major professor, Dr. George Keller, for his patience and help over

An Exploration of Used Fuel Sharing in Multi-Reactor Power Plants

Creator:: Lilley, Benjamin C.
Abstract:: Nuclear fuel management is an optimization problem on many levels. Finding “viable” solutions for the core reload design problem is difficult without expert knowledge and software automation. Small modular reactors with a shared used fuel pool demonstrate a novel opportunity for fuel cycle optimization. A Python package was developed and...
Resource Type:: Dissertation
Full Text:: . Title: An Exploration of Used Fuel Sharing in Multi-Reactor Power Plants Abstract approved: Todd S

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:: approved: Todd S. Palmer During the past few decades, the U.S. Department of Energy (DOE) has made

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:: Modeling of the Minimum Critical Core of the Transient Reactor Test Facility Abstract approved: Dr. Todd

Application of a Modified Microdosimetric-Kinetic Model to Analyze Cell Killing in Determination of the Optimal Particle for Light Ion Therapy

Creator:: Butkus, Michael P.
Abstract:: Ion therapy has long been investigated as a potential modality to improve cancer treatments beyond what is currently feasible with photon irradiations. Ions offer both a physical and biological advantage over photons. The physical advantages are well understood, ions deposit their maximum dose at defined penetration depths, allowing for minimal...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________ Todd S. Palmer Ion therapy has long been investigated as a potential modality to improve

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:: approved: Todd S. Palmer In order to address the energy needs of developing countries and

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:: . I am very grateful to Dr. Andrew Klein and Mr. S. Todd Keller for agreeing to be on the thesis

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:: Target as Fuel. Abstract approved: Todd S. Palmer The most widely used and versatile

ScholarsArchive@OSU

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

The physical properties, consolidation behavior, and stability of the sediments of the Peru-Chile continental margin

Influence of organic matter on the geotechnical properties and consolidation characteristics of northern Oregon continental slope sediments

An Exploration of Used Fuel Sharing in Multi-Reactor Power Plants

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

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

Application of a Modified Microdosimetric-Kinetic Model to Analyze Cell Killing in Determination of the Optimal Particle for Light Ion Therapy

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

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

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

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