Index Catalog // ScholarsArchive@OSU

Predicting antineutrino source terms from a high temperature gas reactor

Creator:: Shaughnessy, Andra L.
Abstract:: Since the 1990s, researchers around the world have been creating antineutrino detectors for monitoring power reactors. These detectors have been deployed at light water reactors and are able to determine power levels and burn up throughout a fuel cycle. This technology could allow the IAEA to monitor LWRs remotely and...
Resource Type:: Masters Thesis
Full Text:: AN ABSTRACT OF THE THESIS OF Andra L. Shaughnessy for the

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

Creator:: Tamashiro, Aaron S.
Abstract:: During the past few decades, the U.S. Department of Energy (DOE) has made significant investments to improve nuclear data libraries, as the quality of this data impacts nearly all analyses of nuclear systems. Nuclear fission product yields are one component of these libraries, and are important for the analysis of...
Resource Type:: Masters Thesis
Full Text:: the Godiva-IV critical assembly in New Mexico in collaboration with Lawrence Livermore National

An inherently parallel Monte Carlo linear systems solver applied to neutron diffusion equations

Creator:: Eccleston, Bradley R.
Abstract:: Linear solvers are often used to solve neutron diffusion problems. These tools have two significant shortcomings. First, parallel implementations provide only a modest speedup. The operations cannot be divided cleanly between processors. Second, for large matrices they can be very slow. Our primary goal is to find a new method...
Resource Type:: Masters Thesis
Full Text:: this work. Many of these individuals are involved in their own research at Lawrence Livermore

A "mildly inconsistent" method for accelerating upstream corner balance transport

Creator:: Gulick, John C.
Abstract:: A new method for accelerating the Upstream Corner Balance (UCB) discretization of the equation of transfer is introduced. The inconsistent acceleration equations for the UCB discretization are derived by applying the "Modified 4-Step" diffusion synthetic acceleration technique not to the UCB discretization, but instead to the simple corner balance (SCB)...
Resource Type:: Masters Thesis
Full Text:: Gentile at Lawrence Livermore National Laboratory. I would like to thank Todd Urbatsch, Tom Evans, Todd

Generation of Multigroup Multiband Cross Sections with Monte Carlo Simulations

Creator:: Lam, Adam Q.
Abstract:: This is the investigation into The generation of high-fidelity multigroup multiband cross sections from Monte Carlo neutron transport simulations. Previous methods for generating multigroup multiband (MGMB) cross sections, and multigroup cross sections, assume an approximate shape for the scalar flux. This approximate flux shape is the product of an energy-dependent...
Resource Type:: Masters Thesis
Full Text:: first internship experience was at Lawrence Livermore National Laboratory. My mentor, Jonathan A. Walsh

Analysis of iteration schemes for deterministic transport in binary Markovian mixtures

Creator:: Ching, Brenton S.
Abstract:: The Adams-Larsen-Pomraning coupled transport model has been used to describe neutral particle transport in binary stochastic mixtures. Here, the mixing statistics are considered to be homogeneous Markovian processes. While the model is robust, the convergence behavior and efficiency of this coupled model have not been addressed. Countless iterative methods could...
Resource Type:: Masters Thesis
Full Text:: (Forest Products). The role of Lawrence Livermore National Laboratory (LLNL) must also be rec- ognized

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:: , φl) + CA−1(m(el, φl)). (2.59) The nonlinear elimination method (NLEM) [34], [35] is applied by

Detection of actinides via nuclear isomer de-excitation

Creator:: Francy, Christopher J.
Abstract:: The detection of illicit weapons-grade nuclear material is a significant technical challenge receiving a great deal of attention in the nuclear community. A proposed solution is to actively bombard the material under investigation with neutrons, populating nuclear isomers in any potential fissile material. These isomers decay quickly, releasing gamma rays...
Resource Type:: Masters Thesis
Full Text:: the beta decay of fission fragments; one such process is being investigated at Lawrence Livermore

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:: Brunner for serving as my mentor during a summer at Lawrence Livermore National Laboratory and giving me

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:: Division at Lawrence Livermore National Laboratory (LLNL) for financially supporting me for the past two

Coarse mesh and one-cell block inversion based diffusion synthetic acceleration

Creator:: Kim, Kang-Seog
Abstract:: DSA (Diffusion Synthetic Acceleration) has been developed to accelerate the SN transport iteration. We have developed solution techniques for the diffusion equations of FLBLD (Fully Lumped Bilinear Discontinuous), SCB (Simple Corner Balance) and UCB (Upstream Corner Balance) modified 4-step DSA in x-y geometry. Our first multi-level method includes a block...
Resource Type:: Dissertation
Full Text:: The research was performed under the contract with Lawrence Livermore National Laboratory. I would

Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling

Creator:: Myers, Nicholas T.
Abstract:: The objective of this thesis was to investigate the use of the Jacobian Free Newton Krylov Method (JFNK) with physics based preconditioning for solving coupled radiative transport and material energy balance. Modeling of these physics is important in inertial confinement fusion and other high energy density systems. In this thesis,...
Resource Type:: Masters Thesis
Full Text:: , t, ν) ∂x ) L + σa(x, ν, TL(x, t)) [EL(x, t, ν)−BL(ν, TL(x, t))−QL(x, t, ν)] (34) FER(x, t, ν

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:: following form: Vig (P) + rg (P)Ig (P) gg (P)Ig (P) + VEjg (P)tg (P). (2-9) g'=l k g=1g'g If we now

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:: career issues has been invaluable. Nick Gentile, my mentor at Lawrence Livermore National Laboratory

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:: project. Thank you to Dr. Tom Brunner for serving as my mentor during a summer at Lawrence Livermore

Accelerated Deterministic Phonon Transport in Lithium Aluminate with Interfacial Scattering Treatment

Creator:: Whitman, Nicholas H.
Abstract:: We present a method for deterministically solving the consistent temperature and frequency dependent phonon radiative transport problem. We use the single relaxation time (SRT) approximation in the Self-Adjoint Angular Flux (SAAF) form with discrete ordinates (S_N) angular discretization method and continuous finite element method (CFEM) for spatial discretization. Included are...
Resource Type:: Dissertation
Full Text:: . . . . . . . . . . . . . . . . . . 75 3.6 Mean-free-path per group Λg in LiAlO2. . . . . . . . . . . . . . . . 76 3.7 Convergence of l

Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios

Creator:: Somasundaram, Elanchezhian
Abstract:: Detection of reactor antineutrinos for non-proliferation applications has been researched extensively across the globe and is considered as a potential technology to remotely monitor reactor operations without any intrusions to reactor components. Reactor antineutrino detection experiments have been conducted in the past and have proven successful in detecting the changes...
Resource Type:: Masters Thesis
Full Text:: Lawrence Livermore National Laboratory (LLNL) in a joint effort. The detector was deployed at the San

Analysis of the antineutrino rate during CANDU reactor startup

Creator:: Matthews, Christopher
Abstract:: Detection systems used to monitor reactor operations are of significant interest as tools for verification of operator declarations. Current reactor site safeguards are limited to visual inspections and intrusive monitoring systems. The recent development of antineutrino detectors may soon allow real-time monitoring from an unobtrusive location. Antineutrinos are produced through...
Resource Type:: Masters Thesis
Full Text:: 1.8 MeV inverse beta decay threshold (Huber, 2004). 1.4 Antineutrino Detectors Lawrence Livermore

Application of a Modified Microdosimetric-Kinetic Model to Analyze Cell Killing in Determination of the Optimal Particle for Light Ion Therapy

Creator:: Butkus, Michael P.
Abstract:: Ion therapy has long been investigated as a potential modality to improve cancer treatments beyond what is currently feasible with photon irradiations. Ions offer both a physical and biological advantage over photons. The physical advantages are well understood, ions deposit their maximum dose at defined penetration depths, allowing for minimal...
Resource Type:: Dissertation
Full Text:: Dynamics Model KERMA Kinetic energy released per unit mass keV kiloelectron volt LBL Lawrence

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Creator:: Brice, Derek J.
Resource Type:: Masters Thesis
Full Text:: a group at Lawrence Livermore National Laboratory [10]. This benchmarking was done using COG, a

Design and analysis of a nuclear reactor core for innovative small light water reactors

Creator:: Soldatov, Alexey I.
Abstract:: In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design...
Resource Type:: Dissertation

ScholarsArchive@OSU

Predicting antineutrino source terms from a high temperature gas reactor

Evaluation of ²³⁵U and ²³⁸U Fast Fission Product Yields from Godiva-IV Burst Irradiation via Gamma Detection

An inherently parallel Monte Carlo linear systems solver applied to neutron diffusion equations

A "mildly inconsistent" method for accelerating upstream corner balance transport

Generation of Multigroup Multiband Cross Sections with Monte Carlo Simulations

Analysis of iteration schemes for deterministic transport in binary Markovian mixtures

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

Detection of actinides via nuclear isomer de-excitation

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

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

Coarse mesh and one-cell block inversion based diffusion synthetic acceleration

Evaluating preconditioning options for the Jacobian-Free Newton Krylov Method applied to radiative transfer with matter coupling

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

The iterative thermal emission Monte Carlo method for thermal radiative transfer

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

Accelerated Deterministic Phonon Transport in Lithium Aluminate with Interfacial Scattering Treatment

Benchmarked simulation of antineutrino source terms for light water reactors during normal operation and diversion scenarios

Analysis of the antineutrino rate during CANDU reactor startup

Application of a Modified Microdosimetric-Kinetic Model to Analyze Cell Killing in Determination of the Optimal Particle for Light Ion Therapy

MCNP model of Sierra Nuclear Corporation dry spent fuel storage containers at Trojan Nuclear Power Plant

Design and analysis of a nuclear reactor core for innovative small light water reactors

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