Index Catalog // ScholarsArchive@OSU

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

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

Numerical Investigation of Unsteady Inertial and Turbulent Flows Through Porous Media: Pore-scale DNS, Flow Analyses and Upscaling

Creator:: He, Xiaoliang
Abstract:: Porous media are the materials containing void space or pores, where fluids and gases can pass through. Unsteady flows in porous media are encountered in many engineering applications and natural problems, such as CO₂ sequestration, high temperature nuclear reactor cooling, high efficiency combustion, chemical reactors, noise reduction on airplane trailing...
Resource Type:: Dissertation
Full Text:: Manufacturing Engineering Dean of the Graduate School I understand that my dissertation will become part of

Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

Creator:: Lam, Adam Q.
Abstract:: In this dissertation, we derive and implement a new transport-diffusion hybrid algorithm for solving thermal radiative transfer (TRT) problems. Using the method of nonlinear elimination (NLEM), the TRT system of equations can be written in terms of a transport equation with the absence of scattering and a diffusion equation. The...
Resource Type:: Dissertation
Full Text:: Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand that

Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

Creator:: Nes, Razvan
Abstract:: An important improvement in the area of reactor core neutronic modeling is the development and use of the methods based on "quasi-diffusion" (QD) low-order equations. This family of methods takes into account the transport exactly using "functionals" computed by solving transport equations, and is amenable to solution with a variety...
Resource Type:: Dissertation
Full Text:: ________________________________________________________________________ Dean of the Graduate School I understand that my dissertation will become part of the

Extending the applicability of implicit Monte Carlo Diffusion : frequency dependence and variance reduction using the difference formulation

Creator:: Cleveland, Mathew A.
Abstract:: The intent of this work is to extend Implicit Monte Carlo Diffusion (IMD)[Gen. 2001] to account for frequency dependence and to incorporate the difference formulation[Szo. 2005] as a source manipulation variance reduction technique. This work shows the derivation of the probabilities and the associated proofs which govern the frequency dependent...
Resource Type:: Masters Thesis
Full Text:: 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

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:: Head of the Department of Nuclear Engineering and Radiation Health Physics Dean of the

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Creator:: Reynolds, Aaron J.
Abstract:: Circulating fuel reactor (CFR) kinetics are characterized by delayed neutron precursor (DNP) drift in addition to the neutronic and thermal hydraulic phenomena typical of other reactor types. This environment can be computationally challenging to model, given that the multiphysics phenomena generally have non-linear interdependencies requiring the use of iterative solution...
Resource Type:: Dissertation
Full Text:: Engineering Head of the School of Nuclear Science and Engineering Dean of the Graduate School I understand

Radiative heat transfer in combustion applications : parallel efficiencies of two gas models, turbulent radiation interactions in particulate laden flows, and coarse mesh finite difference acceleration for improved temporal accuracy

Creator:: Cleveland, Mathew A.
Abstract:: We investigate several aspects of the numerical solution of the radiative transfer equation in the context of coal combustion: the parallel efficiency of two commonly used opacity models, the sensitivity of turbulent radiation interaction (TRI) effects to the presence of coal particulate, and an improvement of the order of temporal...
Resource Type:: Dissertation
Full Text:: and Radiation Health Physics Dean of the Graduate School I understand that my dissertation will

ScholarsArchive@OSU

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

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

Numerical Investigation of Unsteady Inertial and Turbulent Flows Through Porous Media: Pore-scale DNS, Flow Analyses and Upscaling

Diffusion Accelerated Implicit Monte Carlo via Nonlinear Elimination for Thermal Radiative Transfer

Solution of the 2D quasi-diffusion low-order equations using a coupled nodal/finite volume discretization in Cartesian and hexagonal geometry

Extending the applicability of implicit Monte Carlo Diffusion : frequency dependence and variance reduction using the difference formulation

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

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

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Radiative heat transfer in combustion applications : parallel efficiencies of two gas models, turbulent radiation interactions in particulate laden flows, and coarse mesh finite difference acceleration for improved temporal accuracy

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