Index Catalog // ScholarsArchive@OSU

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:: . . . . . . . . . . . . . . . . . . . . . 41 3.1.3 Spatial discretization . . . . . . . . . . . . . . . . . . . . . . 44 3.1.4 Starting angle

Pair production treatments for deterministic pulse-height distribution simulations

Creator:: MacQuigg, Michael R.
Abstract:: This thesis presents methods for treating annihilation photon pairs in deterministic pulse height distribution (PHD) simulations. The methods are applied in PHD simulations for monoenergtic sources of 1.6 and 2.6 MeV photons incident on 5 and 10 cm 1-D slabs of germanium, sodium iodide, and lead and the results are...
Resource Type:: Masters Thesis
Full Text:: Compton-scattered photons. The energy of a photon following a deflection through the angle θ in a Compton

The iterative thermal emission Monte Carlo method for thermal radiative transfer

Creator:: Long, Alex R.
Abstract:: For over 30 years, the Implicit Monte Carlo (IMC) method has been used to solve challenging problems in thermal radiative transfer. These problems are typically optically thick and di ffusive, as a consequence of the high degree of "pseudo-scattering" introduced to model the absorption and reemission of photons from a...
Resource Type:: Masters Thesis
Full Text:: starting position within the basketball, an angle and a speed. The next location where the neutron will

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

Creator:: Woods, Douglas N.
Abstract:: The high-order finite element S[subscript N] transport equations are solved on several test problems to investigate the behavior of the discretization method on meshes with curved edges in X-Y geometry. Simpler problems ensured the correct implementation of MFEM, the general fi nite element library employed. A convergence study using the...
Resource Type:: Masters Thesis
Full Text:: steady-state, monoenergetic radiation transport equation in angle using level-symmetric Gaussian 9

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

Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems

Creator:: Somasundaram, Elanchezhian
Abstract:: The implementation of advanced hybrid (Monte Carlo/Deterministic) transport methods for realistic test problems has been a challenge due to the overhead efforts associated with interfacing a solution generated by a deterministic solver with a Monte Carlo based radiation transport code. In this work, with the help of Transpire, Inc., a...
Resource Type:: Dissertation
Full Text:: methods . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 50 4.3.1 Source biasing with angle

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:: direction of the velocity )I, Projection after i and j axes (i, x, y, z) of ) dQ Unit of the solid angle

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

Creator:: Woods, Douglas N.
Abstract:: We spatially discretize the Sn transport equation using the high-order (HO) discontinuous finite element method (DFEM) on HO meshes. Previous work provided a proof-of-concept for this spatial discretization method in X-Y geometry. Included in the present work, we derive a spatial discretization for the Sn transport equation in both X-Y...
Resource Type:: Dissertation
Full Text:: octant for S6 level-symmetric angular quadrature. . . . . 8 3 Cylindrical space-angle coordinate system

Advanced Deterministic Phonon Transport Techniques for Predicting Spectral Thermal Conductivity in Homogeneous and Heterogeneous Media

Creator:: Harter, Jackson R.
Abstract:: We present a deterministic spectral method to predict equilibrium temperature distributions, heat flux, and thermal conductivity in homogeneous and heterogeneous media. We solve the Boltzmann transport equation in a second order spatial, self-adjoint angular flux formulation. We implemented this method into the radiation transport code Rattlesnake, built using the MOOSE...
Resource Type:: Dissertation
Full Text:: interface, the angle of incidence, its frequency and polarization, and the temperature of both sides of the

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:: = energy ; Ω̂=angle ; t=time A brief background on several time dependent simulation codes that have been

ScholarsArchive@OSU

A Multilevel Nonlinear Projective Method for Circulating Fuel Reactor Kinetics

Pair production treatments for deterministic pulse-height distribution simulations

The iterative thermal emission Monte Carlo method for thermal radiative transfer

High Order Finite Elements SN Transport in X-Y Geometry on Meshes with Curved Surfaces in the Thick Diffusion Limit

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

Application of Advanced Hybrid Transport Methods for Nonproliferation Test Problems

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

Discrete Ordinates Radiation Transport using High-Order Finite Element Spatial Discretizations on Meshes with Curved Surfaces

Advanced Deterministic Phonon Transport Techniques for Predicting Spectral Thermal Conductivity in Homogeneous and Heterogeneous Media

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

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