Index Catalog // ScholarsArchive@OSU

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

Creator:: Law, Tyler
Abstract:: A model of the Oregon State TRIGA reactor was developed in Serpent 2 by translating a previously accepted MCNP model. Both models were verified and validated via comparison of each model and data gathered from the core start-up. Reactivity bias in each code was determined. Using the rod drop method,...
Resource Type:: Masters Thesis
Full Text:: : ______________________________________________________ Steven Reese A model of the Oregon State TRIGA® reactor was developed in Serpent 2 by

Commissioning of the NDDL-40 Neutron Detection System at Oregon State University

Creator:: Boulton, Nicholas M.
Abstract:: The Neutron radiography facility (NRF) at Oregon State University (OSU) has been modified to begin working on the non-destructive evaluation of concrete materials to study the early stages of shrinkage, cracking, and water transport of concrete during the curing process. The objective of this work is to investigate the efficiency...
Resource Type:: Masters Thesis
Full Text:: . Abstract approved: ______________________________________________________ Steven R. Reese The

Neutron radiography and tomography : determining and optimizing resolution of neutron sensitive multi channel plate detectors

Creator:: Williams, Walter James
Abstract:: The objective of this work was to determine and optimize the resolution of a neutron sensitive Multi-Channel Plate (MCP) detector in order to determine its capabilities in radiography and tomography. The Oregon State University, Neutron Radiography Facility added an MCP Detector in 2012 in order to analyze these capabilities. The...
Resource Type:: Masters Thesis
Full Text:: :___________________________________________________ Steven R. Reese The objective of this work was to determine and optimize the resolution of a

MCNP5 modeling of the Oregon State TRIGA Reactor for skyshine dose estimation after a loss of coolant accident

Creator:: Sarmast, Katharine Danielle
Abstract:: This thesis evaluates dose rates from the TRIGA® reactor by comparing ion chamber measured exposure rates to exposure rates calculated from MCNP5 model data. The first step evaluates the energy distribution required to match ion chamber exposure rates from measurements taken at 1 foot increments above the reactor core. Next,...
Resource Type:: Masters Thesis
Full Text:: approved: Steve R. Reese This thesis evaluates dose rates from the TRIGA® reactor by

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

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

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:: The author expresses sincere appreciation to Dr. Steven Reese for the opportunity to collaborate on

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:: thank my advisor, Dr. Steven Reese, for providing me with the opportunity to work on this project and

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:: Steven R. Reese Natural uranium samples were irradiated in-core for 7 seconds using the pneumatic

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

ScholarsArchive@OSU

Benchmark comparison of the Oregon State TRIGA reactor between MCNP6 and Serpent 2

Commissioning of the NDDL-40 Neutron Detection System at Oregon State University

Neutron radiography and tomography : determining and optimizing resolution of neutron sensitive multi channel plate detectors

MCNP5 modeling of the Oregon State TRIGA Reactor for skyshine dose estimation after a loss of coolant accident

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

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

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

Creating Anthropomorphic Models with Mesh Phantoms in MCNP to Simulate Mammography

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

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

Limit your search

Academic Affiliation

Advisor

Commencement Year

Committee Member

Creator

Date

Decade

Degree Field

Degree Level

Degree Name

Language

License

Non-Academic Affiliation

Peer Reviewed

Resource Type

Rights Statement

Subject

Search Constraints

Search Results

Limit your search