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...
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Todd S. Palmer
Transport in a binary stochastic media has been an area of interest for many
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...
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...
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...
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...
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...
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...
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...
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...
The scattering of optical rays by small spherical particles bears a strong resemblance to the
diffusion of fission neutrons in solid materials. This work explores the feasibility of
exploiting similarities between these two systems for the purposes of reactor component analysis, education, and outreach. After a brief overview of reactor-environment...