Index Catalog // ScholarsArchive@OSU

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

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

Multi-Scale, Multi-Physics Reactor Pulse Simulation Method with Macroscopic and Microscopic Feedback Effects

Creator:: Zabriskie, Adam X.
Abstract:: The Transient Reactor Test facility (TREAT) at Idaho National Laboratory (INL) is a unique reactor capable of stressing test fuel during a power pulse transient. TREAT fuel is composed of high enriched uranium (HEU) heterogeneous fuel; microscopic UO₂ fuel grains with an average radius of 10 μm are randomly distributed...
Resource Type:: Dissertation
Full Text:: weighted arithmetic mean is 𝑋 = ∑ 𝑤 𝑋 ∑ 𝑤 , 1 with 𝑋 denoting the value being homogenized, 𝑤 is

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

Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts

Creator:: Nakagawa, Ayako
Abstract:: Influences of operating conditions on the production of carbon nanotubes (CNTs) were studied using Fe and Fe-Ni bimetallic catalysts supported on silicon monoxide (SiO). The catalysts were prepared in three steps: (1) impregnation of SiO powders with ferric nitride or combinations of ferric and nickel nitrides, (2) oxidation of nitrides...
Resource Type:: Masters Thesis

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

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

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:: [ T ri lli o n k W h ] OECD China Russia India Non−OECD remainder Figure 1.1

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

Radioxenon generation using highly enriched uranium

Creator:: Elliott, Anthony James
Abstract:: This work focuses on the generation and collection of four specific radioxenon isotopes; xenon-131m, xenon-133m, xenon-133 and xenon-135. These nuclides are created by fissioning a highly enriched uranium sample using a thermal neutron source from a university research reactor. The three main aspects of this work include: (1) Conducting preliminary...
Resource Type:: Masters Thesis
Full Text:: like to thank Todd Keller for helping me with the reactor approval process and design phases of my

ScholarsArchive@OSU

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

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

Multi-Scale, Multi-Physics Reactor Pulse Simulation Method with Macroscopic and Microscopic Feedback Effects

Inter-code Comparison of Time Independent Pulsed Sphere Benchmark Results

Catalytic chemical vapor deposition synthesis of carbon nanotubes from methane on SiO supported Fe and Fe−Ni catalysts

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

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

Fission Gas Bubble Behavior in Uranium Carbide

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

Radioxenon generation using highly enriched uranium

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