Index Catalog // ScholarsArchive@OSU

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

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Creator:: Lenhof, Renae
Abstract:: A limited scope Probabilistic Risk Assessment (PRA) of a vented nuclear fuel system for a Generation IV Gas-Cooled Fast Reactor Plant was performed. The goal of the study was to better understand the safety and licensing implications of vented fuel technology. A Level 1 PRA was performed to determine the...
Resource Type:: Masters Thesis

Retrospective thermal neutron fluence determination using lithium-ion mobile telephone batteries

Creator:: Dorrell, Nick J.
Abstract:: Fortuitous dosimeters are radiosensitive objects carried by an individual who was exposed to radiation. These objects can be analyzed some time after exposure and the results can be used to aid in calculating radiation fields and doses received by individuals. Items that make good fortuitous dosimeters are those that are...
Resource Type:: Masters Thesis
Full Text:: AN ABSTRACT OF THE THESIS OF Nick J. Dorrell for the

CFD analysis of pressure differentials in a plate-type fuel assembly

Creator:: Roth, Gable D.
Abstract:: The Hydro-Mechanical Fuel Test Facility (HMFTF) is being built at Oregon State University to evaluate fluid flow through plate-type fuel assemblies. The first plate assembly that will be examined in the facility is the Generic Test Plate Assembly (GTPA). The GTPA consists of an array of six parallel flat plates,...
Resource Type:: Masters Thesis
Full Text:: . I would like to thank Dr. Jamie Kruzic and Dr. Susan Carozza for agreeing to be on my committee. I

An analysis of the prompt effects of an indoor, non-explosive radiological dispersal device utilizing cesium-137 or cobalt-60

Creator:: Melnick, Stefan T.
Abstract:: The advances in the nuclear sciences over the past sixty years have yielded many beneficial technologies and applications, such as power generation, food irradiation, and medical diagnostic devices and techniques. However, these advances have also allowed the advent of nuclear and radiological weapons. This paper will focus on one type...
Resource Type:: Masters Thesis

Calculation of Pulse height distributions from deterministic transport simulations

Creator:: Benz, Jacob M.
Abstract:: In source-detector radiation transport simulations, pulse height distributions are a useful metric in assessing the effectiveness of nuclear instrumentation. In the area of spectroscopy, pulse height distributions are used to identify an unknown source. It is widely believed that pulse height distributions cannot be created using deterministic methods. This quantity...
Resource Type:: Masters Thesis
Full Text:: : )()( )( )()1( )1( xQx x x jj nt j n n         , n = 1... N (2.10) ,)()( 2

Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor

Creator:: Brigantic, Adam
Abstract:: Small modular reactors (SMRs) are a recent advancement in commercial nuclear reactor design with growing interest worldwide. New SMR concepts, such as the Multi-Application Small Light Water Reactor (MASLWR), must undergo a licensing processes established by the U.S. Nuclear Regulatory Commission (NRC) prior to commercial operation. Given the lack of...
Resource Type:: Masters Thesis

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:: ) where Ti,N = ( i−1∑ j=1 T n+1j ) + (N − i+ 1)T ni . (42) 28 The Ti,N term is the current

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:: Dr. Jamie J Kruzic, who have helped me with development of the research concepts and ideas, and

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

Creator:: Mai, Anh T.
Abstract:: The Multi-Application Small Light Water Reactor (MASLWR) is a small natural circulation pressurized light water reactor design that was developed by Oregon State University (OSU) and Idaho National Engineering and Environmental Laboratory (INEEL) under the Nuclear Energy Research Initiative (NERI) program to address the growing demand for energy and electricity....
Resource Type:: Masters Thesis
Full Text:: with Dr. Wu on the MASLWR Test Facility. I would like to thank Dr. Leah Minc and Dr. Jamie Kruzic

ScholarsArchive@OSU

Analysis of the antineutrino rate during CANDU reactor startup

Probabilistic risk assessment of a vented fuel system utilized in a generation IV gas-cooled fast reactor nuclear power plant

Retrospective thermal neutron fluence determination using lithium-ion mobile telephone batteries

CFD analysis of pressure differentials in a plate-type fuel assembly

An analysis of the prompt effects of an indoor, non-explosive radiological dispersal device utilizing cesium-137 or cobalt-60

Calculation of Pulse height distributions from deterministic transport simulations

Applying uncertainty and sensitivity on thermal hydraulic subchannel analysis for the multi-application small light water reactor

The iterative thermal emission Monte Carlo method for thermal radiative transfer

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

Thermal hydraulic and fuel performance analysis for innovative small light water reactor using VIPRE-01 and FRAPCON-3

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