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Articles 1 - 14 of 14
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Uranium Holdup Mass Quantification By Hybrid Gamma Imaging, Blake R. Montz
Uranium Holdup Mass Quantification By Hybrid Gamma Imaging, Blake R. Montz
Masters Theses
Accurate quantification of uranium holdup is crucial in the efficient operation of many processing facilities involved with special nuclear material (SNM). The varying shapes and sizes of holdup deposits can make accurate quantification a challenge. The most common approach is the Generalized Geometry Holdup (GGH) method which simplifies the shape of the deposit to a point, line, or area source. Although the GGH method is quick and easy to implement, the oversimplifying assumptions can lead to systematic uncertainties as high as 50%. The research presented here is exploring gamma-ray imaging as a more accurate method of quantifying deposits. A PHDs …
Development Of A Low-Dose Radiation Therapy Device For Acute Respritory Distress Syndrome, Thomas Heath Davis
Development Of A Low-Dose Radiation Therapy Device For Acute Respritory Distress Syndrome, Thomas Heath Davis
Masters Theses
This research focuses on the development of a low dose radiotherapy (LD-RT) device for treatment of acute respiratory distress syndrome (ARDS), a respiratory illness that affects millions of people a year. The use of orthovoltage (200 – 500 keV) X-ray energy provides many advantages over traditional radiotherapy delivery with linear accelerators, such as low cost and greater accessibility. In addition, X-ray tubes have been shown throughout history to provide good treatment outcomes for pneumonia, and research has shown LD-RT to be just as effective with ARDS. This proposal summarizes my efforts in determining the dosimetric properties of a LD-RT system …
Component Monitoring Strategies For Ipwr Plant Systems During Operational Transients, Matthew S. Scott
Component Monitoring Strategies For Ipwr Plant Systems During Operational Transients, Matthew S. Scott
Masters Theses
Small modular reactors (SMRs) are currently at the forefront of the nuclear industry as potential next stage in nuclear energy production. Implementing a new reactor technology in a commercial setting contains many challenges in terms of maintaining safety and regulatory standards since all of the regulatory framework is based on the traditional PWR design. One benefit of the SMR design is the increased ability to load-follow to meet the constant changes in grid demand. This type of operational strategy introduces changes into the system that impacts the operational lifespan of system components due to increased degradation. Since there are no …
Modeling The Reactor Time-Dependent Delayed Particle Tail With Monte Carlo N-Particle (Mcnp) Version 6.2, Eli James Boland
Modeling The Reactor Time-Dependent Delayed Particle Tail With Monte Carlo N-Particle (Mcnp) Version 6.2, Eli James Boland
Masters Theses
"Energy is deposited into experiment packages due to post-shutdown decay heat created from delayed particles. Modeling these delayed particles in a reactor assists researchers in quantifying the expected energy deposition sources to an experiment package before irradiation. This paper focuses on modeling the delayed particles in a reactor in MCNP6.2 by capturing a reactor as a source, converting this source capture to a source definition, applying appropriate physics such as activation and photonuclear interactions, and finally using proper tallies to create the expected delayed particle tail of a reactor.
To capture the source distribution, the FMESH capability within MCNP was …
Fire Simulation And Analysis Of A Switchgear Cabinet Fire And Its Effects On Cable Trays, Yalcin Meraki
Fire Simulation And Analysis Of A Switchgear Cabinet Fire And Its Effects On Cable Trays, Yalcin Meraki
Masters Theses
Switchgear rooms are crucial in containing essential equipment such as cabinets and cable trays in case of a possible fire. There are three fire model classes which are algebraic models, zone model, and computation fluid dynamics model (CFD). PyroSim software, a visual user interface for the Fire Dynamics Simulator (FDS) developed at the National Institute of Standards and Technology (NIST), was used for simulation by using the CFD. Two different 464 kW and 1002 kW heat release rate (HRR) values were used under the same conditions for the fire scenario. By considering a fire scenario, the fire ignited due to …
Design And Evaluation Of A Unique Weighted-Sum-Based Anger Camera, Matthew W. Seals
Design And Evaluation Of A Unique Weighted-Sum-Based Anger Camera, Matthew W. Seals
Masters Theses
Anger camera imaging technology has become widely popular for neutron diffraction imaging due to recent shortages in Helium-3 (He-3). Research into neutron diffraction optimized Anger camera by the Oak Ridge National Laboratory (ORNL) detectors group has provided an alternative to He-3 Tube-based detectors with a high-resolution Anger camera. However, the cost of these high-resolution Anger camera technology can make it less attractive than He-3 tubes when a large Field of View (FOV) is desired. Currently, there is a need for a lower-cost alternative to this high-resolution anger camera. Further applications for Anger camera have become of interest with the advent …
Development Of Codoped Cesium Iodide Scintillators For Medical Imaging Applications, Everett M. Cavanaugh
Development Of Codoped Cesium Iodide Scintillators For Medical Imaging Applications, Everett M. Cavanaugh
Masters Theses
Cesium iodide has a rich history of use as a scintillating material. CsI finds use in a variety of fields, but it is primarily used in radiography, tomography, and geological exploration. Of the three common variants of CsI, thallium doped CsI is by far the most widely used among these applications. It possesses favorable physical characteristics like a high density and high effective Z and exhibits high light output at room temperature. Despite how great CsI scintillators may be on paper, they have an Achilles heel: afterglow. CsI:Tl has significant afterglow which leads to imaging artifacts that can be difficult …
Enigma - Ongoing Development Towards Novel Beta-Decay Spectroscopy Station At Isolde, Philipp Wagenknecht
Enigma - Ongoing Development Towards Novel Beta-Decay Spectroscopy Station At Isolde, Philipp Wagenknecht
Masters Theses
Beta decay and collinear laser spectroscopy are proven efficient tools to study nuclear structure far from stability. Two areas of significance are investigations into nuclear deformation and shape coexistence, as well as delayed neutron emissions used in nuclear energy applications. This contribution presents the ongoing development towards a novel beta-decay spectroscopy station for the VITO experiment at CERN’s radioactive ion beam facility ISOLDE. The setup will utilize both collinear laser spectroscopy and beta-decay spectroscopy to measure the energy and spin-parities of the ground and excited states of radioactive beams. Initial designs of the support structure, magnetic field, and detector array …
Validation Of Relap5-3d For Transient Simulation Of Lead-Lithium Systems For Fusion Applications, Nicholas Akira Meehan
Validation Of Relap5-3d For Transient Simulation Of Lead-Lithium Systems For Fusion Applications, Nicholas Akira Meehan
Masters Theses
With increasing development in fusion technology including the construction and subsequently planned experimental campaign of the International Thermonuclear Experimental Reactor (ITER), validation must be performed for simulation tools used in the design, development, and licensing of future commercial fusion systems. This thesis contains several validation studies for transient simulation of lead-lithium eutectic (PbLi) systems using the RELAP5-3D code. This validation analysis is performed initially using models of systems without the influence of a magnetic field to inspect heat transfer and pressure drop phenomena. The validation study then uses models of systems under the influence of a magnetic field to inspect …
Meta-Heuristic Optimization Techniques For The Production Of Medical Isotopes Through Special Target Design, Cameron Ian Salyer
Meta-Heuristic Optimization Techniques For The Production Of Medical Isotopes Through Special Target Design, Cameron Ian Salyer
Masters Theses
Medical isotopes are used for a variety of different diagnostic and therapeutic purposes Ruth (2008). Due to recent newly discovered applications, their production has become rapidly more scarce than ever before Charlton (2019). Therefore, more efficient and less time consuming methods are of interest for not only the industry’s demand, but for the individuals who require radio-isotope procedures. Currently, the primary source of most medical isotopes used today are provided by reactor and cyclotron irradiation techniques, followed by supplemental radio-chemical separations Ruth (2008). Up until this point, target designs have been optimized by experience, back of the envelope calculations, and …
Particle Swarm Optimization For Critical Experiment Design, Cole Michael Kostelac
Particle Swarm Optimization For Critical Experiment Design, Cole Michael Kostelac
Masters Theses
“Critical experiments are used by nuclear data evaluators and criticality safety engineers to validate nuclear data and computational methods. Many of these experiments are designed to maximize the sensitivity to a certain nuclide-reaction pair in an energy range of interest. Traditionally, a parameter sweep is conducted over a set of experimental variables to find a configuration that is critical and maximally sensitive. As additional variables are added, the total number of configurations increases exponentially and quickly becomes prohibitively computationally expensive to calculate, especially using Monte Carlo methods.
This work presents the development of a particle swarm optimization algorithm to design …
Validation Of Athlet-Cd With Cora-28 Test, Murat Tuter
Validation Of Athlet-Cd With Cora-28 Test, Murat Tuter
Masters Theses
“Following the incidents at Chernobyl and Fukushima, severe accidents at nuclear power plants (NPP) have become a global concern. These accidents generally occur because of a failure in the reactor cooling system (RCS) and result in the melting of the reactor core and fission product release. This event is mostly caused by a LOCA, loss of flow accident, station blackout or loss of heat sink. During a severe accident, generation of hydrogen as a result of steam-zircaloy fuel cladding is a significant safety concern. To better understand and prevent the hydrogen generation issue, safety related experiments and safety related codes …
Characterization Of Cermet Fuel For Nuclear Thermal Propulsion (Ntp), James Floyd Mudd
Characterization Of Cermet Fuel For Nuclear Thermal Propulsion (Ntp), James Floyd Mudd
Masters Theses
“A manned flight to Mars is met with many technical challenges, not the least of which is the development of propulsion technology capable of moving a transit vehicle from Earth orbit to Mars orbit. NASA is investigating Nuclear Thermal Propulsion (NTP) as a way of reducing flight time and providing the option for a mid-mission abort. NTP, which uses a high temperature nuclear reactor to heat a propellant, requires advanced fuel materials capable of withstanding temperatures well in excess of 2000 K. Among the fuel options are ceramic metal (cermet) composites composed of refractory metals and Ultra-High Temperature Ceramics (UHTCs). …
Feasibility Of A Critical Experiment Utilizing Uranium Dioxide-Beryllium Oxide With Neutron Spectrum Shifting Capabilities, Ashley Rachel Raster
Feasibility Of A Critical Experiment Utilizing Uranium Dioxide-Beryllium Oxide With Neutron Spectrum Shifting Capabilities, Ashley Rachel Raster
Masters Theses
“The goal of this project is to determine the feasibility of utilizing Annular Core Research Reactor (ACRR) fuel in core design with Sandia Pulse Reactor Facility’s (SPRF) Seven Percent Critical Experiment (7uPCX) fuel rods as driver fuel for a critical experiment facility to support future critical and benchmark experiments for the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook. This is part of the Critical Experiment Design (CED) process for future criticality experiments. These criticality experiment designs have the main goal of being performed in the same facility at different neutron energy ranges. To test the feasibility of this experiment …