Index Catalog // ScholarsArchive@OSU

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

Prompt gamma neutron activation analysis of niobium for characterization of light interstitials

Creator:: Love, Ian J.
Abstract:: High purity niobium metal is used in the construction of superconducting radio frequency (SRF) cavities in superconducting particle accelerators, such as the Large Hadron Collider (LHC) at CERN or the Spallation Neutron Source (SNS) at Oak Ridge National Laboratory. The usual method for characterizing the impurities in this niobium, the...
Resource Type:: Masters Thesis
Full Text:: ABSTRACT OF THE THESIS OF Ian J. Love for the degree of Master of Science in Materials Science

Measurement of 239Pu, 237Np, and 238U Fission Product γ Rays

Creator:: Tamashiro, Aaron S.
Abstract:: Fission product yields (FPYs) are used for a wide range of applications including nuclear fission theory, nuclear reactor design, reactor antineutrino anomaly, stellar nucleosynthesis, and nuclear forensics. These applications rely on FPYs that were last evaluated in 1993, which included measurements from all over the world up until 1993. In...
Resource Type:: Dissertation
Full Text:: . Title: Measurement of 239Pu, 237Np, and 238U Fission Product γ Rays Abstract approved: Camille J

Developing Software Tools to Characterize Electrochemical Loss Scenarios via Gamma Detection for Various Measurement Points, Source Geometries, and Process Times

Creator:: Harris, Noah C.
Abstract:: Faithful modeling of the expected gamma signals inside an electrochemical facility at various key measurement points is important for understanding what detection limits are available for the next generation of safeguards technologies. Gamma Detector Response and Analysis Software (GADRAS) and the Separation Safeguards Performance Model (SSPM) were used to build...
Resource Type:: Masters Thesis

Human Eye Dosimetry: Air Gap Analysis by Shield Placement and Photon Energy

Creator:: Herrera, Joshua P.
Abstract:: When the ICRP updated their recommended limits for eye dose, they ignited a renewed interest in eye dosimetry. Especially, how the updated eye dose estimates affect current regulations and what that would mean to a radiation worker. Radiation workers are commonly required to wear leaded eyeglasses to reduce their dose...
Resource Type:: Masters Thesis
Full Text:: ...................................................................... 51 Appendix Figures J: 14 cm Photon Energy to Dose Curve

Eye Lens Doses from Oblique Sources

Creator:: Trakowski, Ian M.
Abstract:: Since the International Commission on Radiation Protection (ICRP) recommended a revision to the eye lens dose limits in ICRP Publication 118 (Stewart, 2012) the radiation protection community has conducted many new studies related to eye dosimetry. The recommended reduction of eye lens dose limits may result in the reduction of...
Resource Type:: Masters Thesis

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

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

Creator:: Lilley, Benjamin C.
Abstract:: Material testing experiments are needed to enable the next generation of nuclear fission reactors. Concluding in 2009, the Boosted Fast Flux Loop (BFFL) project was devised as a way to test fast reactor materials and fuels in the Advanced Test Reactor (ATR), however the experiment location it used is now...
Resource Type:: Masters Thesis
Full Text:: reactor analysis,” Tech. rep., Argonne National Lab.(ANL), Argonne, IL (United States) (2013). [2] J. L

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

Creator:: Kumar, Ravi
Abstract:: In this thesis, we expand the scope of a previously introduced Artificial Neural Network (ANN) method to solve the slab-geometry discrete ordinates (S$_N$) neutron transport equations. Specifically, we extend the method to energy-dependent (multi-group) fixed source problems involving heterogeneous media and more general boundary conditions - vacuum and incident flux...
Resource Type:: Masters Thesis
Full Text:: can be used to estimate the number of neutrons passing through an area dA at a point r: j(r, E,Ω, t

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

Creator:: Latimer, Griffen D.
Abstract:: Current research on the topic of advanced reactor fuel types include the use of ultrahigh density Uranium-Molybdenum fuels, towards their use in high-performance research reactors. These reactors operate with high power densities, and the increased cooling requirements therefore place high relevance on the fluid-structure interaction with these fuel elements; therefore...
Resource Type:: Masters Thesis
Full Text:: ......................................................... 47 Table 5: Values of δj, μj, and κj

ScholarsArchive@OSU

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

Prompt gamma neutron activation analysis of niobium for characterization of light interstitials

Measurement of 239Pu, 237Np, and 238U Fission Product γ Rays

Developing Software Tools to Characterize Electrochemical Loss Scenarios via Gamma Detection for Various Measurement Points, Source Geometries, and Process Times

Human Eye Dosimetry: Air Gap Analysis by Shield Placement and Photon Energy

Eye Lens Doses from Oblique Sources

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

Neutronic Analysis of a Liquid Metal Fast Reactor Experiment in the Large-I Position of the Advanced Test Reactor

A Study of Artificial Neural Networks for the Solution of Multi-group Slab Geometry Discrete Ordinates Transport Problems with Material Heterogeneity

Vibration Analysis of Advanced Test Reactor Miniplate Hydraulic Test in the OSU HMFTF

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