Index Catalog // ScholarsArchive@OSU

Extending the discrete maximum principle for the IMC equations

Creator:: Talbot, Paul W.
Abstract:: The implicit Monte Carlo (IMC) method [16] for radiative transfer, developed in 1971, provides numerical solutions to the tightly-coupled, highly-nonlinear radiative heat transfer equations in many physical situations. Despite its popularity, there are instances of overheating in the solution for particular choices of time steps and spatial grid sizes. To...
Resource Type:: Masters Thesis
Full Text:: Equations AN ABSTRACT OF THE THESIS OF Paul W. Talbot for the degree of Master of Science in Nuclear

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:: :____________________________________________________ Todd S. Palmer An important improvement in the area of reactor core neutronic modeling is the

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:: Accuracy Abstract approved: Todd S. Palmer We investigate several aspects of the numerical solution of

Binary stochastic media transport : a coupled mesh based method

Creator:: Barnett, Nathan A.
Abstract:: Transport in a binary stochastic media has been an area of interest for many applications over the past three decades. Many different methods have been attempted, most based on the Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve problems where a large amount of...
Resource Type:: Masters Thesis
Full Text:: : __________________________________________________________________ Todd S. Palmer Transport in a binary stochastic media has been an area of interest for many

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:: . Abstract approved: _____________________________________________________________________ Todd S

Radiation health and safety of a radioisotope powered micro fuel cell

Creator:: Maloy, Kyle James
Abstract:: Radiation health and safety issues associated with a plutonium-powered radioisotope powered micro fuel cell (RMFC) were evaluated. The RMFC converts water into its component elements by radiolysis and the resultant hydrogen is used to power the fuel cell. This device is under development and is being considered for possible deployment...
Resource Type:: Masters Thesis
Full Text:: . Todd Palmer Radiation health and safety issues associated with a plutonium-powered radioisotope

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

Investigation of a hybrid quasi-diffusion/Monte Carlo method for solving multigroup criticality problems in slab geometry

Creator:: Robinson, Bethany R.
Abstract:: A hybrid Quasi-diffusion/Monte Carlo Method for solving multigroup criticality problems in slab geometry was investigated. Analog Monte Carlo was used to calculate functionals (Eddington Factors) that were then used in solution of the quasi-diffusion equations. The hybrid method was shown to accurately and precisely predict the k-eigenvalue and fission source...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: Todd S. Palmer A hybrid Quasi-diffusion/Monte Carlo Method for solving multigroup

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:: Formulation. Abstract approved: Todd S. Palmer The intent of this work is to extend Implicit Monte Carlo

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

ScholarsArchive@OSU

Extending the discrete maximum principle for the IMC equations

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

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

Binary stochastic media transport : a coupled mesh based method

Simulated antineutrino signatures of nuclear reactors for nonproliferation applications

Radiation health and safety of a radioisotope powered micro fuel cell

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

Investigation of a hybrid quasi-diffusion/Monte Carlo method for solving multigroup criticality problems in slab geometry

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

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

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