Index Catalog // ScholarsArchive@OSU

MCNP 6 Simulations of Short-Lived, Low-Yield Fission Byproducts, Gamma-Ray Spectrometry, and their Comparison to Natural Uranium Measurements for the Evaluation of Available Evaluated Nuclear Data Files

Creator:: Jeffries, Tanner D.
Abstract:: Natural uranium samples were irradiated in-core for 7 seconds using the pneumatic rabbit system within the TRIGA Mark II Reactor at Oregon State University, and then used to generate a gamma-ray spectrum with a high purity germanium (HPGe) detector. The irradiated sample was simulated in Monte Carlo N-Particle (MCNP), a...
Resource Type:: Masters Thesis
Full Text:: AN ABSTRACT FOR THE THESIS OF Tanner D. Jeffries for

Transforming Protective Action Strategies for Radiological Emergencies—Exacting the Science of Sheltering-in-Place

Creator:: Smith, Todd R.
Abstract:: Radiological emergency plans ensure that protective actions can and will be taken in the event of an accident. Principle protective actions for the early phase of an emergency are evacuation and sheltering-in-place. While evacuations are generally safe, there are deterministic, long-term health consequences from prolonged displacement that outweigh the stochastic...
Resource Type:: Masters Thesis
Full Text:: -Place. Abstract approved: ______________________________________________________ Steven R

SCALE 6 (TRITON) Simulations of Fission Product Gamma Line Emissions and their Comparison to Plutonium and Uranium Measurements

Creator:: Sanchez, Timothy J.
Abstract:: Thin foil samples of special nuclear materials (SNMs) were irradiated for 60s using a Mark TRIGA II reactor, and their associated gamma emissions were recorded with a count time of 60s following irradiation. A rapid pneumatic transfer system was used to irradiate the samples in front of beam port #4....
Resource Type:: Masters Thesis
Full Text:: Plutonium and Uranium Measurements. Abstract approved: Steven R. Reese Thin foil samples of

Neutron Flux-Energy Spectral Characterization of a Deuterium-Tritium Neutron Generator at Oregon State University

Creator:: Eastman, Abigail L.
Abstract:: The neutron flux-energy spectral characterization of a Thermo Fisher MP320 deuterium-tritium neutron generator was performed for two shielding configurations, one with substantial moderator between the source and the sample and one without such moderator. The STAYSL PNNL spectral adjustment code was utilized in conjunction with MCNP modelled reference spectra and...
Resource Type:: Masters Thesis
Full Text:: University Abstract approved: Steven R. Reese The neutron flux-energy spectral characterization of a

Temporal gamma-ray spectrometry to quantify relative fissile material content

Creator:: Williford, Russell S.
Abstract:: A new method for delayed gamma-ray spectrometry to quantify the relative content of fissile material is developed and demonstrated to support international efforts in bolstering non-destructive assay capabilities. Previous traditional delayed gamma-ray spectrometry techniques rely upon nuclear data that often carry very high uncertainty. The new method removes the requirement...
Resource Type:: Dissertation
Full Text:: : Steven R. Reese A new method for delayed gamma-ray spectrometry to quantify the relative content

Special Nuclear Material Analysis Using Temporal Gamma-Ray Spectroscopy and Machine Learning Methods

Creator:: Curtis, Jessica R.
Abstract:: Following thermal neutron induced fission, supervised machine learning and temporal gamma-ray spectroscopy methods were used to identify differences in the delayed gamma-ray spectra of Pu-239 and U-235. The temporal gamma-ray spectroscopy method takes advantage of the time-dependent decay of fission products. Employing Spearman's rank-order correlation coefficient and without prior knowledge...
Resource Type:: Masters Thesis
Full Text:: approved: Steven R. Reese Following thermal neutron induced fission, supervised machine learning and

Exploring Novel Contrast Agents with Anthropomorphic Mesh Models in MCNP

Creator:: Garcia, Jacqueline K.
Abstract:: Breast cancer is the leading cancer in women with an estimated 13% of women in the United States developing a form of invasive breast cancer in her lifetime. The survival rate is estimated to be 85%, but the American Cancer Society estimates that early detection of breast cancer in the...
Resource Type:: Dissertation
Full Text:: : ______________________________________________________ Steven Reese Abstract: Breast cancer is the leading cancer in women with an estimated 13

Creating Anthropomorphic Models with Mesh Phantoms in MCNP to Simulate Mammography

Creator:: Garcia, Jacqueline K.
Abstract:: Breast cancer is the most common cancer among women as it accounts for about 25% of all female cancer cases. Studies have shown that early detection of breast cancer increases the chances of a positive prognosis amongst patients therefore it is crucial to provide accurate diagnosis tools in routine exams....
Resource Type:: Masters Thesis
Full Text:: Mammography Abstract approved: ______________________________________________________________ Steven R

Neutron Attenuation and Hydration of Cement Paste made with Light and Heavy Water

Creator:: Goodwin, Margaret N.
Abstract:: Neutron radiography has been used to study cementitious materials. This thesis studies the impact of heavy water on both the rate of hydration and neutron radiography. The neutron attenuation coefficients of light and heavy water were measured. Cement pastes were made with both heavy and light water. The attenuation coefficients...
Resource Type:: Masters Thesis
Full Text:: Abstract approved: ______________________________________________________ Steven R. Reese

Control Rod Shadowing Effects in Control Rod Calibrations of The Oregon State TRIGA® Reactor

Creator:: Spoerer, Tracey T.
Abstract:: Control rod calibration experiment results for the Oregon State TRIGA® Reactor (OSTR) immediately following LEU conversion in 2008, and MCNP® 5 predicted rod worths from the 2008 LEU Conversion Safety Analysis Report (CSAR) are discussed. The reactivity worth of the four OSTR control rods are measured using the rod-pull method....
Resource Type:: Masters Thesis
Full Text:: . Abstract approved: ______________________________________________________ Steven Reese

ScholarsArchive@OSU

MCNP 6 Simulations of Short-Lived, Low-Yield Fission Byproducts, Gamma-Ray Spectrometry, and their Comparison to Natural Uranium Measurements for the Evaluation of Available Evaluated Nuclear Data Files

Transforming Protective Action Strategies for Radiological Emergencies—Exacting the Science of Sheltering-in-Place

SCALE 6 (TRITON) Simulations of Fission Product Gamma Line Emissions and their Comparison to Plutonium and Uranium Measurements

Neutron Flux-Energy Spectral Characterization of a Deuterium-Tritium Neutron Generator at Oregon State University

Temporal gamma-ray spectrometry to quantify relative fissile material content

Special Nuclear Material Analysis Using Temporal Gamma-Ray Spectroscopy and Machine Learning Methods

Exploring Novel Contrast Agents with Anthropomorphic Mesh Models in MCNP

Creating Anthropomorphic Models with Mesh Phantoms in MCNP to Simulate Mammography

Neutron Attenuation and Hydration of Cement Paste made with Light and Heavy Water

Control Rod Shadowing Effects in Control Rod Calibrations of The Oregon State TRIGA® Reactor

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