Index Catalog // ScholarsArchive@OSU

CO2 reduction in aqueous-ionic liquid solution in microscale-based corona reactor, CO₂ reduction in aqueous-ionic liquid solution in microscale-based corona reactor

Creator:: Miao, Yu
Abstract:: Global warming problem is becoming an increasingly important environmental concern and CO₂ is considered as the major cause of global warming. Among various methods of CO₂ utilization, conversion of CO₂ to value added chemical products is the most attractive. In this study, a microscale-based corona reactor is introduced for reduction...
Resource Type:: Masters Thesis
Full Text:: me to accomplish this degree. I would also like to thank Dr. Liney Árnadóttir and Dr. Todd

Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility

Creator:: Tang, Hong
Abstract:: Natural convection provides a means for circulating fluids without the use of pumps. This type of system is of great interest for a wide variety of applications, including solar heaters, process industry, and nuclear reactors. Natural convection will play a vital role in the area of passive safety and reliability,...
Resource Type:: Masters Thesis
Full Text:: committee, Dr. Todd S. Palmer and Dr. Vinod Narayanan, for their valuable comments and their time. I also

Inter-code Comparison of Time Independent Pulsed Sphere Benchmark Results

Creator:: Northrop, Jordan
Abstract:: The pulsed sphere benchmark problems are a set of physical experiments that have been used to verify Monte Carlo codes and evaluate nuclear data. All Monte Carlo codes rely on benchmark experiments that test the features of the code to verify that the simulations are producing realistic results. In the...
Resource Type:: Honors College Thesis
Full Text:: : Camille Palmer, Mentor, representing Nuclear Engineering Todd Palmer, Committee Member, representing

Characterization of the onset of charged particle equilibrium for photon dose to skin

Creator:: Ryan, Michael C.
Abstract:: In the U.S., the Nuclear Regulatory Commission (NRC) is responsible for setting annual dose limits. For cases of hot particle contamination these limits are set at depths in skin of 7 mg/cm², 300 mg/cm², and 1000 mg/cm². However, at such shallow depths, the lack of charged particle equilibrium (CPE) precludes...
Resource Type:: Masters Thesis
Full Text:: OOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOOO (2K/443!A5!P9>/97!S#'(T!/>!:3>@97

Feasibility of Enrichment Measurements with a Pixelated CdTe HEXITEC Detector: A Comparison of Methods

Creator:: Kasparek, Dustin
Abstract:: The International Atomic Energy Agency (IAEA) is responsible for verifying the mass of elemental uranium in various forms (powders, pellets, scrap) as part of safeguards inspections at nuclear fuel fabrication facilities in support of the nuclear non-proliferation treaty. Current methods require in-field dissolution chemistry, which is time consuming and imposes...
Resource Type:: Masters Thesis
Full Text:: : Camille Palmer The International Atomic Energy Agency (IAEA) is responsible for verifying the mass of

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Creator:: Onufer, Mark
Abstract:: The International Handbook of Evaluated Reactor Physics Benchmark Experiments contains detailed descriptions of many different reactor facilities. A large portion of these experiments have not been fully modeled due to the unavailability of computational power at the time of the experiment’s execution. With the advent of renewed interest in Sodium...
Resource Type:: Masters Thesis

Fission Gas Bubble Behavior in Uranium Carbide

Creator:: Matthews, Christopher
Abstract:: The need for cheap reliable energy, while simultaneously avoiding uranium supply constraints makes uranium carbide (UC) fueled Gas Fast Reactors offer an attractive nuclear reactor design. In order to qualify the fuel, an enhanced understanding of the behavior of uranium carbide during operation is paramount. Due to a reduced re-solution...
Resource Type:: Dissertation
Full Text:: . Palmer who first brought me to Oregon State University. I am appreciative of The Fringe research group

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
Full Text:: General Atomics during the 1960’s and 70’s 5 . The fuel design consisted of stainless steel cladding and

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Creator:: Castañeda, Juan A.
Abstract:: In early 2000, the Generation IV International Forum (GIF) was created to perform research and development for the next generation nuclear systems. Among the selected nuclear systems was the Very High Temperature Gas-Cooled Reactor (VHTR). Then in 2008, the U.S. Department of Energy (DOE) decided that the Next Generation Nuclear...
Resource Type:: Masters Thesis
Full Text:: would like to thank Dr. Todd Palmer for taking the time from his busy schedule to be part of my

Epithermal neutron beam design at the Oregon State University TRIGA Mark II reactor (OSTR) based on Monte Carlo methods

Creator:: Tiyapun, Kanokrat
Resource Type:: Masters Thesis
Full Text:: drafts. I would like to thank the member of my committees: Dr. Roy D. Haggerty, Dr. Todd S. Palmer and

ScholarsArchive@OSU

CO2 reduction in aqueous-ionic liquid solution in microscale-based corona reactor, CO₂ reduction in aqueous-ionic liquid solution in microscale-based corona reactor

Stability analysis on single-phase natural circulation in Argonne Lead Loop Facility

Inter-code Comparison of Time Independent Pulsed Sphere Benchmark Results

Characterization of the onset of charged particle equilibrium for photon dose to skin

Feasibility of Enrichment Measurements with a Pixelated CdTe HEXITEC Detector: A Comparison of Methods

An MCNP benchmark model of the large experimental ZPPR-19B sodium fast reactor

Fission Gas Bubble Behavior in Uranium Carbide

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

Scaling analysis of the OSU high temperature test facility during a pressurized conduction cooldown event using RELAP5-3D

Epithermal neutron beam design at the Oregon State University TRIGA Mark II reactor (OSTR) based on Monte Carlo methods

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