Index Catalog // ScholarsArchive@OSU

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
Full Text:: 0 Department of Nuclear Engineering And

Performance of hybrid methods for representative nonproliferationproblems

Creator:: Bevill, Aaron M.
Abstract:: Adjoint-derived weight windowing is a hybrid deterministic/Monte Carlo method to simulate radiation transport. In adjoint-derived weight windowing, a deterministic adjoint solution is used to create weight windows for a Monte Carlo simulation. The intent of this work is to identify factors that reduce the Figure of Merit (FOM) of Monte...
Resource Type:: Masters Thesis
Full Text:: of Master of Science in Nuclear Engineering pre- sented on May 13, 2011. Title: Performance of Hybrid

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:: for the degree of Master of Science in Nuclear Engineering presented on January 27, 2012. Title

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:: Somasundaram for the degree of Master of Science in Nuclear Engineering presented on October 7, 2011

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:: Science in Nuclear Engineering pre- sented on August 9, 2000. Title: Analysis of Iteration Schemes for

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:: degree of Master of Science in Nuclear Engineering pre- sented on May 18, 2011. Title: Evaluating

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

Creator:: Strohecker, Mark F.
Abstract:: The OSU/APEX thermal hydraulic test facility models the passive safety systems of the Westinghouse AP600 advanced light water reactor design. Numerous experiments have been performed to test these systems, the one of focus here is the station blackout scenario. This experiment simulated the complete loss of AC power to all...
Resource Type:: Masters Thesis
Full Text:: for the degree of Master of Science in Nuclear Engineering presented on April 21, 1998. Title

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

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:: Master of Science in Nuclear Engineering presented on June 1 2012. Title: The Iterative Thermal Emission

Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry

Creator:: Hummel, Andrew J.
Abstract:: Reactor modeling is largely limited by the computational time required to perform accurate full core calculations. There are many different methods and techniques employed in different reactor simulation codes, but properly modeling all of the physics that takes place in the system requires extensive computational effort. The Coarse Mesh Finite...
Resource Type:: Masters Thesis
Full Text:: Andrew J. Hummel for the degree of Master of Science in Nuclear Engineering presented on December 17

ScholarsArchive@OSU

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

Performance of hybrid methods for representative nonproliferationproblems

Analysis of the antineutrino rate during CANDU reactor startup

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

Analysis of iteration schemes for deterministic transport in binary Markovian mixtures

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

Investigation of the IRWST flow patterns during a simulated station blackout experiment on the OSU APEX facility

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

The iterative thermal emission Monte Carlo method for thermal radiative transfer

Accelerating the convergence of the k-eigenvalue problem using a coarse mesh finite differencing scheme in cylindrical geometry

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