Index Catalog // ScholarsArchive@OSU

An assessment of a mesh-based method for slab-geometry transport in stochastic materials

Creator:: Bassett, Brody R.
Abstract:: There exists a variety of methods to solve the radiation transport equation in stochastic materials, including the Levermore-Pomraning method and the atomic mix method, each of which is designed to replicate the results given by benchmarks with materials rearranged in a randomized fashion. While the atomic mix method is very...
Resource Type:: Masters Thesis
Full Text:: transport. The atomic mix model can have large errors, as stochastic e�ects such as the likelihood of

Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups

Creator:: Davis, Ian M. (Ian Mack)
Abstract:: Benchmark calculations are performed for neutron transport in a two material (binary) stochastic multiplying medium. Spatial, angular, and energy dependence are included. The problem considered is based on a fuel assembly of a common pressurized water nuclear reactor. The mean chord length through the assembly is determined and used as...
Resource Type:: Masters Thesis
Full Text:: Master of Science in Nuclear Engineering presented on March 10, 2005. Title: Neutron Transport Benchmarks

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:: One- Group Diffusion Theory Model) 48 5.8 Assembly Power Densities for the 2-D Benchmark Problem

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:: neutron flux provided by the transport code Attila. Two-group macroscopic cross-sections are extracted

An advanced nodal discretization for the quasi-diffusion low-order equations

Creator:: Nes, Razvan
Abstract:: The subject of this thesis is the development of a nodal discretization of the low-order quasi-diffusion (QDLO) equations for global reactor core calculations. The advantage of quasi-diffusion (QD) is that it is able to capture transport effects at the surface between unlike fuel assemblies better than the diffusion approximation. We...
Resource Type:: Masters Thesis
Full Text:: METHOD FOR NEUTRON TRANSPORT 7 2.1. TRANSPORT PRELIMINARIES 7 2.2. DERIVATION OF LOW ORDER QUASI

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:: Levermore-Pomraning coupled transport model. However, this method has never been able to correctly solve

Analysis of the method of tubes characteristic schemes in the thick diffusive limit

Creator:: Rising, Michael E.
Abstract:: Characteristic methods are widely known to be very accurate approaches to the solution of numerical transport problems. These methods are most often used for neutron transport applications (i.e. lattice physics calculations) where spatial cells are of intermediate optical thickness (O(1) - O(100) mean free paths, depending on the energy group)...
Resource Type:: Masters Thesis
Full Text:: problems. These methods are most often used for neutron transport applications (i.e. lattice physics

Reactive transport modeling in a discrete fracture : applications to the formation of sericitic hydrothermal alteration at Butte, Montana

Creator:: Geiger, Sebastian
Abstract:: A model for the spatial and temporal evolution of the gray sericitic (GS) and sericite with remnant biotite (SBr) hydrothermal alteration selvages within the Butte Quartz Monzonite (BQM) of the porphyry copper deposit at Butte, Montana, is presented. The model provides a mathematical description for the location and advance of...
Resource Type:: Masters Thesis
Full Text:: , Montana, is presented. The model provides a mathematical description for the location and advance of

A novel lattice Boltzmann method for treatment of multicomponent convection, diffusion, and reaction phenomena in multiphase systems

Creator:: Parker, James Muirhead
Abstract:: In this work, a multicomponent lattice Boltzmann model is developed for the simulation of multiphase mixing, reactions, and separations processes. This model is unique in that diffusive mass transfer of a component in the model is driven by gradients of chemical potential. This fundamentally correct description of diffusion accurately captures...
Resource Type:: Dissertation
Full Text:: the One-Dimensional Model . . . . . . . . . . . . . 39 3.1.3 Transport Coefficients of the One

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:: . For instance, in neutron transport the cross section of a material typically has different

ScholarsArchive@OSU

An assessment of a mesh-based method for slab-geometry transport in stochastic materials

Neutron transport benchmarks for binary stochastic multiplying media : planar geometry, two energy groups

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

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

An advanced nodal discretization for the quasi-diffusion low-order equations

Binary stochastic media transport : a coupled mesh based method

Analysis of the method of tubes characteristic schemes in the thick diffusive limit

Reactive transport modeling in a discrete fracture : applications to the formation of sericitic hydrothermal alteration at Butte, Montana

A novel lattice Boltzmann method for treatment of multicomponent convection, diffusion, and reaction phenomena in multiphase systems

Extending the discrete maximum principle for the IMC equations

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